WorldWideScience

Sample records for research facility operated

  1. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-01-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. The authors emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities

  2. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-10-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

  3. Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

    International Nuclear Information System (INIS)

    Bissani, M; O'Kelly, D S

    2006-01-01

    A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to provide color-enhanced gemstones but is

  4. Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; O' Kelly, D S

    2006-05-08

    A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to

  5. Remote operations in a Fusion Engineering Research Facility (FERF)

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1975-01-01

    The proposed Fusion Engineering Research Facility (FERF) has been designed for the test and evaluation of materials that will be exposed to the hostile radiation environment created by fusion reactors. Because the FERF itself must create a very hostile radiation environment, extensive remote handling procedures will be required as part of its routine operations as well as for both scheduled and unscheduled maintenance. This report analyzes the remote-handling implications of a vertical- rather than horizontal-orientation of the FERF magnet, describes the specific remote-handling facilities of the proposed FERF installation and compares the FERF remote-handling system with several other existing and proposed facilities. (U.S.)

  6. Safe operation of existing radioactive waste management facilities at Dalat Nuclear Research Institute

    International Nuclear Information System (INIS)

    Pham Van Lam; Ong Van Ngoc; Nguyen Thi Nang

    2000-01-01

    The Dalat Nuclear Research Reactor was reconstructed from the former TRIGA MARK-II in 1982 and put into operation in March 1984. The combined technology for radioactive waste management was newly designed and put into operation in 1984. The system for radioactive waste management at the Dalat Nuclear Research Institute (DNRI) consists of radioactive liquid waste treatment station and disposal facilities. The treatment methods used for radioactive liquid waste are coagulation and precipitation, mechanical filtering and ion- exchange. Near-surface disposal of radioactive wastes is practiced at DNRI In the disposal facilities eight concrete pits are constructed for solidification and disposal of low level radioactive waste. Many types of waste generated in DNRI and in some Nuclear Medicine Departments in the South of Vietnam are stored in the disposal facilities. The solidification of sludge has been done by cementation. Hydraulic compactor has done volume reduction of compatible waste. This paper presents fifteen-years of safe operation of radioactive waste management facilities at DNRI. (author)

  7. 77 FR 68155 - The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R-84

    Science.gov (United States)

    2012-11-15

    ... Research Institute TRIGA Reactor: Facility Operating License No. R-84 AGENCY: Nuclear Regulatory Commission... considering an application for the renewal of Facility Operating License No. R-84 (Application), which... the renewal of Facility Operating License No. R-84, which currently authorizes the licensee to operate...

  8. EnergySolution's Clive Disposal Facility Operational Research Model - 13475

    Energy Technology Data Exchange (ETDEWEB)

    Nissley, Paul; Berry, Joanne [EnergySolutions, 2345 Stevens Dr. Richland, WA 99354 (United States)

    2013-07-01

    EnergySolutions owns and operates a licensed, commercial low-level radioactive waste disposal facility located in Clive, Utah. The Clive site receives low-level radioactive waste from various locations within the United States via bulk truck, containerised truck, enclosed truck, bulk rail-cars, rail boxcars, and rail inter-modals. Waste packages are unloaded, characterized, processed, and disposed of at the Clive site. Examples of low-level radioactive waste arriving at Clive include, but are not limited to, contaminated soil/debris, spent nuclear power plant components, and medical waste. Generators of low-level radioactive waste typically include nuclear power plants, hospitals, national laboratories, and various United States government operated waste sites. Over the past few years, poor economic conditions have significantly reduced the number of shipments to Clive. With less revenue coming in from processing shipments, Clive needed to keep its expenses down if it was going to maintain past levels of profitability. The Operational Research group of EnergySolutions were asked to develop a simulation model to help identify any improvement opportunities that would increase overall operating efficiency and reduce costs at the Clive Facility. The Clive operations research model simulates the receipt, movement, and processing requirements of shipments arriving at the facility. The model includes shipment schedules, processing times of various waste types, labor requirements, shift schedules, and site equipment availability. The Clive operations research model has been developed using the WITNESS{sup TM} process simulation software, which is developed by the Lanner Group. The major goals of this project were to: - identify processing bottlenecks that could reduce the turnaround time from shipment arrival to disposal; - evaluate the use (or idle time) of labor and equipment; - project future operational requirements under different forecasted scenarios. By identifying

  9. Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Goldhagen, P.; Marino, S.A.; Randers-Pehrson, G.; Hall, E.J.

    1986-01-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which can be used to generate a variety of well-characterized radiation beams for research in radiobiology and radiological physics. It is part of the Radiological Research Laboratory (RRL), and its operation is supported as a National Facility by the US Department of Energy. RARAF is available to all potential users on an equal basis, with priorities based on the recommendations of a Scientific Advisory Committee. Facilities and services are provided to users, but the research projects themselves must be supported separately. This chapter presents a brief description of current experiments being carried out at RARAF and of the operation of the Facility from January through June, 1986. Operation of the Facility for all of 1985 was described in the 1985 Progress Report for RARAF. The experiments described here were supported by various Grants and Contracts from NIH and DOE and by the Statens Stralskyddsinstitut of Sweden

  10. Space facilities: Meeting future needs for research, development, and operations

    Science.gov (United States)

    The National Facilities Study (NFS) represents an interagency effort to develop a comprehensive and integrated long-term plan for world-class aeronautical and space facilities that meet current and projected needs for commercial and government aerospace research and development and space operations. At the request of NASA and the DOD, the National Research Council's Committee on Space Facilities has reviewed the space related findings of the NFS. The inventory of more than 2800 facilities will be an important resource, especially if it continues to be updated and maintained as the NFS report recommends. The data in the inventory provide the basis for a much better understanding of the resources available in the national facilities infrastructure, as well as extensive information on which to base rational decisions about current and future facilities needs. The working groups have used the inventory data and other information to make a set of recommendations that include estimates of cast savings and steps for implementation. While it is natural that the NFS focused on cost reduction and consolidations, such a study is most useful to future planning if it gives equal weight to guiding the direction of future facilities needed to satisfy legitimate national aspirations. Even in the context of cost reduction through facilities closures and consolidations, the study is timid about recognizing and proposing program changes and realignments of roles and missions to capture what could be significant savings and increased effectiveness. The recommendations of the Committee on Space Facilities are driven by the clear need to be more realistic and precise both in recognizing current incentives and disincentives in the aerospace industry and in forecasting future conditions for U.S. space activities.

  11. Initial operation of the Holifield facility

    International Nuclear Information System (INIS)

    Ball, J.B.

    1982-01-01

    The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new Pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

  12. Initial operation of the Holifield Facility

    International Nuclear Information System (INIS)

    Ball, J.B.

    1983-01-01

    The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

  13. 77 FR 7613 - Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108

    Science.gov (United States)

    2012-02-13

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-264; NRC-2012-0026] Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108 AGENCY: Nuclear Regulatory Commission... Facility Operating License No. R-108 (``Application''), which currently authorizes the Dow Chemical Company...

  14. Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report October 1-December 31, 2016

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, Jimmy [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-01-01

    Individual datastreams from instrumentation at the U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile research observatories (sites) are collected and routed to the ARM Data Center (ADC). The Data Management Facility (DMF), a component of the ADC, executes datastream processing in near-real time. Processed data are then delivered approximately daily to the ARM Data Archive, also a component of the ADC, where they are made freely available to the research community. For each instrument, ARM calculates the ratio of the actual number of processed data records received daily at the ARM Data Archive to the expected number of data records. DOE requires national user facilities to report time-based operating data.

  15. Establishment and Operation of User Facilities

    International Nuclear Information System (INIS)

    Cho, Yong Sub; Kwon, Hyeok Jung; Kim, Kye Ryung

    2008-05-01

    PEFP(Proton Engineering Frontier Project) has launched on a new enterprise to develop the technologies for the future relating to the proton beam and spin-off technologies in 2002. PEFP planned to supply 20MeV and 100MeV proton beam by the development of the 100MeV, 20mA linear accelerator during ten years from 2002 to 2012. The final goal of this project is establishment of 20MeV and 100MeV user facilities. To do this, we must develop the key technologies for establishing user facilities. Before the main facilities are normally operated, we have established the test user facilities to support various kinds of users' basic experiments and pilot studies. The necessity of this research are as follows; - Domestic achievement of key technologies for the development and design of the user facilities for the several tens to hundreds MeV class high current proton beam - Beam application researches can be revitalized and improved the efficiency by the establishment and operation of user facilities and test facilities. - Ion implantation facilities have contributed to increase Industrial applications - It is more effective in saving money that users use the PEFP's user facility than other country's user facilities. - It is possible to contribute to the local society and commercialize the beam application technologies by the establishment of PEFP's research branch in Kyungju

  16. Designing Facilities for Collaborative Operations

    Science.gov (United States)

    Norris, Jeffrey; Powell, Mark; Backes, Paul; Steinke, Robert; Tso, Kam; Wales, Roxana

    2003-01-01

    ; at worst, operational performance would deteriorate. Elements of this methodology were applied to the design of three operations facilities for a series of rover field tests. These tests were observed by human-factors researchers and their conclusions are being used to refine and extend the methodology to be used in the final design of the MER operations facility. Further work is underway to evaluate the use of personal digital assistant (PDA) units as portable input interfaces and communication devices in future mission operations facilities. A PDA equipped for wireless communication and Ethernet, Bluetooth, or another networking technology would cost less than a complete computer system, and would enable a collaborator to communicate electronically with computers and with other collaborators while moving freely within the virtual environment created by a shared immersive graphical display.

  17. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.

    1992-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis, and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. Experiments performed from May 1991--April 1992 are described

  18. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1991-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis, and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. Brief summaries of research experiments are included. Accelerator usage is summarized and development activities are discussed. 8 refs., 8 tabs

  19. Development and Operation of Experiment Course using Research Reactor and Associated Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Shin, B. C.; Hwang, I. A.; Won, J. Y.; Ju, Y. C.; Nam, J. S.; Seo, K. W.; Kim, H. N.

    2013-05-15

    The purpose of present research is to offer a specialized educational opportunity by developing specific curriculum for potential users, mainly university students majoring in related with nuclear engineering and radiation field, on site at KAERI, exploiting the diverse offering of HANARO and ancillary facilities. The specific items of this research accomplished are: First, Development of various curricula for specific research using HANARO and continuous operation of the developed curricula to provided university students with opportunities to use HANARO. Second, Continuous operation of research reactor related experimental training programs for university students in nuclear field to make contribution to cultivating specialists. Third, through the site experimental training for new coming nuclear engineering students, support future potential users to the nuclear research fields, as well as enlarge or broaden the base. Finally, it is hoped that these experiments broadens public awareness and acceptance of the present and potential future contribution of the reactor technology, there by bring positive impacts to policy making. As a whole, 108 students offered and 88 students from 6 universities have completed the course of the programs developed by this project. Also, 1 textbook and 1 teaching aid, a questionnaire have been developed to support the program.

  20. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1993-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) - formerly the Radiological Research Laboratory of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. This report provides a listing and brief description of experiments performed at RARAF during the May 1, 1992 through April 30, 1993

  1. Facility design, construction, and operation

    International Nuclear Information System (INIS)

    1995-04-01

    France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l'Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l'Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec's contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides' all of the basic information in these areas and reflects actual experience to date

  2. Operation of Cryogenic Facility in e-way at Tata Institute of Fundamental Research, Mumbai, India

    International Nuclear Information System (INIS)

    Srinivasan, K V

    2012-01-01

    In an attempt towards the development of modern, model and paperless cryogenic facility, the Low Temperature Facility of Tata Institute of Fundamental Research, at Mumbai, India; carried out many automation works using programmable logic controller (PLC) and other modern electronic tools, with the objective of bringing the entire plant operation to your palm whenever and wherever you are. Efficiency in the plant operation by keeping a watch on the plant healthiness, advance indication about the possible plant problem by means of pre-warning alarms, so that the remedial action can be taken well prior to the actual failure affects the plant operation, reduction in plant down time were achieved by the automation works. Large size in our cryogen production, controlling the complicated helium liquefier, meeting the uninterrupted supply of cryogen to the users on “any time availability basis,” safety in handling cryogens and high pressure gas, effective usage of limited skilled manpower etc., all these requirements call for the definite need of modern electronic gears and gadgets. This paper will describe in details about the automation works carried out at our cryogenic facility at TIFR.

  3. The Valduc waste incineration facility starts operations (iris process)

    International Nuclear Information System (INIS)

    Chateauvieux, H.; Guiberteuau, P.; Longuet, T.; Lannaud, J.; Lorich, M.

    1998-01-01

    In the operation of its facilities the Valduc Research Center produces alpha-contaminated solid waste and thus decided to build an incineration facility to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run in 1997. The operator conducted tests with calibrated radioactive sources to qualify the systems for measuring holdup of active material from outside the equipment. Chlorinated waste incineration test runs were performed using the phosphatizing process developed by the Marcoule Research Center. Inspections performed after these incineration runs revealed the complete absence of corrosion in the equipment. Active commissioning of the facility is scheduled for mid-1998. The Valduc incinerator is the first industrial application of the IRIS process. (author)

  4. Creation of a new-generation research nuclear facility

    International Nuclear Information System (INIS)

    Girchenko, A.A.; Matyushin, A.P.; Kudryavtsev, E.M.; Skopin, V.P.; Shchepelev, R.M.

    2013-01-01

    The SO-2M research nuclear facility operated on the industrial area of the institute. The facility is now removed from service. In view of this circumstance, it is proposed to restore the facility at the new qualitative level, i.e., to create a new-generation research nuclear facility with a very high safety level consisting of a subcritical bench and a proton accelerator (electronuclear facility). Competitive advantages and design features have been discussed and the productive capacity of the research nuclear facility under development has been evaluated [ru

  5. Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

    International Nuclear Information System (INIS)

    Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

    1997-01-01

    A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs

  6. Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

    Energy Technology Data Exchange (ETDEWEB)

    Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

    1997-01-01

    A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs.

  7. The Radiological Research Accelerator Facility:

    International Nuclear Information System (INIS)

    Hall, E.J.; Goldhagen, P.

    1988-07-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generated a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Radiological Research Laboratory (RRL) of Columbia University, and its operation is supported as a National Facility by the U.S. Department of Energy. As such, RARAF is available to all potential users on an equal basis, and scientists outside the RRL are encouraged to submit proposals for experiments at RARAF. Facilities and services are provided to users, but the research projects themselves must be supported separately. RARAF was located at BNL from 1967 until 1980, when it was dismantled and moved to the Nevis Laboratories of Columbia University, where it was then reassembled and put back into operation. Data obtained from experiment using RARAF have been of pragmatic value to radiation protection and to neutron therapy. At a more fundamental level, the research at RARAF has provided insight into the biological action of radiation and especially its relation to energy distribution in the cell. High-LET radiations are an agent of special importance because they can cause measurable cellular effects by single particles, eliminating some of the complexities of multievent action and more clearly disclosing basic features. This applies particularly to radiation carcinogenesis. Facilities are available at RARAF for exposing objects to different radiations having a wide range of linear energy transfers (LETs)

  8. Design and operations at the National Tritium Labelling Facility

    International Nuclear Information System (INIS)

    Morimoto, H.; Williams, P.G.

    1991-09-01

    The National Tritium Labelling Facility (NTLF) is a multipurpose facility engaged in tritium labeling research. It offers to the biomedical research community a fully equipped laboratory for the synthesis and analysis of tritium labeled compounds. The design of the tritiation system, its operations and some labeling techniques are presented

  9. Annual Report of Radioactive Waste Facilities Operation in 2013

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; GAO; Zhi-gang; LIU; Fu-guo

    2013-01-01

    301,a section of Department of Radiochemistry,which manages 15 facilities and undertakes the administrative tasks of radioactive waste,is the important guarantee of scientific research production and safety in CIAE.1 The safe operation of the radioactive waste management facilities In 2013,in order to ensure the operation safety,we formulated the inspection regulations,which included regular operation inspection,week safety inspection from the leaders of the section and

  10. Applied Operations Research: Operator's Assistant

    Science.gov (United States)

    Cole, Stuart K.

    2015-01-01

    NASA operates high value critical equipment (HVCE) that requires trouble shooting, periodic maintenance and continued monitoring by Operations staff. The complexity HVCE and information required to maintain and trouble shoot HVCE to assure continued mission success as paper is voluminous. Training on new HVCE is commensurate with the need for equipment maintenance. LaRC Research Directorate has undertaken a proactive research to support Operations staff by initiation of the development and prototyping an electronic computer based portable maintenance aid (Operator's Assistant). This research established a goal with multiple objectives and a working prototype was developed. The research identified affordable solutions; constraints; demonstrated use of commercial off the shelf software; use of the US Coast Guard maintenance solution; NASA Procedure Representation Language; and the identification of computer system strategies; where these demonstrations and capabilities support the Operator, and maintenance. The results revealed validation against measures of effectiveness and overall proved a substantial training and capability sustainment tool. The research indicated that the OA could be deployed operationally at the LaRC Compressor Station with an expectation of satisfactorily results and to obtain additional lessons learned prior to deployment at other LaRC Research Directorate Facilities. The research revealed projected cost and time savings.

  11. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1990-07-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). Fifteen different experiments were run during these 12 months, approximately the same as the previous two years. Brief summaries of each experiment are included. Accelerator usage is summarized and development activities are discussed. 7 refs., 4 tabs

  12. Confinement Physics Research Facility/ZTH: A progress report

    International Nuclear Information System (INIS)

    Hammer, C.F.; Thullen, P.

    1989-01-01

    In October 1985 the Los Alamos National Laboratory's Controlled Thermonuclear Research (CTR) Division began the design and construction of the Confinement Physics Research Facility (CPRF) and the ZTH toroidal, reversed-field-pinch (RFP), plasma physics experiment. The CPRF is a facility which will provide the buildings, utilities, pulsed power system, control system and diagnostics needed to operate a magnetically confined fusion experiment, and ZTH will be the first experiment operated in the facility. The construction of CPRF/ZTH is scheduled for completion in the first quarter of 1993. 5 figs

  13. Advanced Control Test Operation (ACTO) facility

    International Nuclear Information System (INIS)

    Ball, S.J.

    1987-01-01

    The Advanced Control Test Operation (ACTO) project, sponsored by the US Department of Energy (DOE), is being developed to enable the latest modern technology, automation, and advanced control methods to be incorporated into nuclear power plants. The facility is proposed as a national multi-user center for advanced control development and testing to be completed in 1991. The facility will support a wide variety of reactor concepts, and will be used by researchers from Oak Ridge National Laboratory (ORNL), plus scientists and engineers from industry, other national laboratories, universities, and utilities. ACTO will also include telecommunication facilities for remote users

  14. 77 FR 26321 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112

    Science.gov (United States)

    2012-05-03

    ... Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY: Nuclear Regulatory Commission... Commission (NRC or the Commission) has issued renewed Facility Operating License No. R- 112, held by Reed... License No. R-112 will expire 20 years from its date of issuance. The renewed facility operating license...

  15. Radiological dose assessment from the operation of Daeduk nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil [Korea Atomic Energy Research Institute, Taejon (Korea)

    2000-02-01

    The objective of this project is to assure the public acceptance for nuclear facilities, and the environmental safety from the operation of Daeduk nuclear facilities, such as HANARO research reactor, nuclear fuel processing facilities and others. For identifying the integrity of their facilities, the maximum individual doses at the site boundary and on the areas with high population density were assessed. Also, the collective doses within radius 80 km from the site were assessed. The radiation impacts for residents around the site from the operation of Daeduk nuclear facilities in 1999 were neglectable. 8 refs., 10 figs., 27 tabs. (Author)

  16. Research Facilities for the Future of Nuclear Energy

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1996-01-01

    The proceedings of the ENS Class 1 Topical Meeting on Research facilities for the Future of Nuclear Energy include contributions on large research facilities, designed for tests in the field of nuclear energy production. In particular, issues related to facilities supporting research and development programmes in connection to the operation of nuclear power plants as well as the development of new concepts in material testing, nuclear data measurement, code validation, fuel cycle, reprocessing, and waste disposal are discussed. The proceedings contain 63 papers

  17. General problems specific to hot nuclear materials research facilities

    International Nuclear Information System (INIS)

    Bart, G.

    1996-01-01

    During the sixties, governments have installed hot nuclear materials research facilities to characterize highly radioactive materials, to describe their in-pile behaviour, to develop and test new reactor core components, and to provide the industry with radioisotopes. Since then, the attitude towards the nuclear option has drastically changed and resources have become very tight. Within the changed political environment, the national research centres have defined new objectives. Given budgetary constraints, nuclear facilities have to co-operate internationally and to look for third party research assignments. The paper discusses the problems and needs within experimental nuclear research facilities as well as industrial requirements. Special emphasis is on cultural topics (definition of the scope of nuclear research facilities, the search for competitive advantages, and operational requirements), social aspects (overageing of personnel, recruitment, and training of new staff), safety related administrative and technical issues, and research needs for expertise and state of the art analytical infrastructure

  18. Report on operation of nuclear facilities in Slovenia in 1991

    International Nuclear Information System (INIS)

    1992-11-01

    Slovenian Nuclear Safety Administration (SNSA) is responsible for: nuclear safety, transport of nuclear and radioactive materials, safeguarding nuclear materials, and conducting regulatory process related to liability for nuclear damage, qualification and training of operators at nuclear facilities, quality assurance and inspection of nuclear facilities. The major nuclear facility supervised by SNSA is the Nuclear Power Plant in Krsko with a pressurized water reactor of 632 MW electric power. Beside the nuclear power plant, TRIGA Mark 11 Research Reactor of 250 kW thermal power operates within the Reactor Center of Jozef Stefan Institute. There is an interim storage of low and medium radioactive waste at the Reactor Center. Also the Uranium mine Zirovski Vrh was supervised by SNSA. All the nuclear power facilities in Republic of Slovenia were operating safely in 1991. There were no significant events that could be evaluated as a safety problem or a breach of technical specifications. A great part of activities of SNSA was focused on the next visit of the IAEA OSART team (Operational Safety Assessment Review Team) in Krsko Nuclear Power Plant and on the visit of the INSARR mission (Integrated Safety Assessment of Research Reactors) for the TRIGA Mark 11 Research Reactor. (author)

  19. Operational status of nuclear facilities in Japan. 2012 edition

    International Nuclear Information System (INIS)

    2012-01-01

    This document is a compilation which provides an outline of the administration of nuclear facility safety regulations as well as various data including operational status, the status of periodical and safety inspections, the status of issues, and radiation management on nuclear power reactor facilities, reactor facilities in the research and development stage, and fabrication, reprocessing, disposal, and storage facilities in fiscal year 2011 (from April 2011 to March 2012). (J.P.N.)

  20. Nuclear Facilities Management Section Mutsu Office, Aomori Research and Development Center operations report. FY 2012 and 2013

    International Nuclear Information System (INIS)

    Tajima, Yoshihiro; Kuwabara, Jun; Oyokawa, Atsushi; Kabuto, Shoji; Araya, Naoyuki; Kikuchi, Kaoru; Miyamoto, Shingo; Nemoto, Hideyuki; Ohe, Osamu

    2016-05-01

    Nuclear Facilities Management Section implements the operation, maintenance and decommissioning of the first nuclear ship “MUTSU” and the operation and maintenance of the liquid waste facility and the solid waste facility where a small amount of nuclear fuel is used. This is the report on the operations of the Nuclear Facilities Management Section for FY 2012 and FY 2013. (author)

  1. 50 Years of the Radiological Research Accelerator Facility (RARAF)

    OpenAIRE

    Marino, Stephen A.

    2017-01-01

    The Radiological Research Accelerator Facility (RARAF) is in its 50th year of operation. It was commissioned on April 1, 1967 as a collaboration between the Radiological Research Laboratory (RRL) of Columbia University, and members of the Medical Research Center of Brookhaven National Laboratory (BNL). It was initially funded as a user facility for radiobiology and radiological physics, concentrating on monoenergetic neutrons. Facilities for irradiation with MeV light charged particles were d...

  2. The Sanford Underground Research Facility at Homestake

    International Nuclear Information System (INIS)

    Heise, J.

    2015-01-01

    The former Homestake gold mine in Lead, South Dakota, has been transformed into a dedicated facility to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e.) and currently hosts two main physics projects: the LUX dark matter experiment and the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment. In addition, two low-background counters currently operate at the Davis Campus in support of current and future experiments. Expansion of the underground laboratory space is underway at the 4850L Ross Campus in order to maintain and enhance low-background assay capabilities as well as to host a unique nuclear astrophysics accelerator facility. Plans to accommodate other future experiments at SURF are also underway and include the next generation of direct-search dark matter experiments and the Fermilab-led international long-baseline neutrino program. Planning to understand the infrastructure developments necessary to accommodate these future projects is well advanced and in some cases have already started. SURF is a dedicated research facility with significant expansion capability

  3. The Sanford Underground Research Facility at Homestake

    International Nuclear Information System (INIS)

    Heise, J

    2015-01-01

    The former Homestakegold mine in Lead, South Dakota has been transformed into a dedicated facility to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e.) and currently hosts two main physics projects: the LUX dark matter experiment and the MAJORANA DEMONSTRATOR neutrinolessdouble-beta decay experiment. In addition, two low-background counters currently operate at the Davis Campus in support of current and future experiments. Expansion of the underground laboratory space is underway at the 4850L Ross Campus in order to maintain and enhance low- background assay capabilities as well as to host a unique nuclear astrophysics accelerator facility. Plans to accommodate other future experiments at SURF are also underway and include the next generation of direct-search dark matter experiments and the Fermilab-led international long- baseline neutrino program. Planning to understand the infrastructure developments necessary to accommodate these future projects is well advanced and in some cases have already started. SURF is a dedicated research facility with significant expansion capability. (paper)

  4. A Framework for Managing Core Facilities within the Research Enterprise

    OpenAIRE

    Haley, Rand

    2009-01-01

    Core facilities represent increasingly important operational and strategic components of institutions' research enterprises, especially in biomolecular science and engineering disciplines. With this realization, many research institutions are placing more attention on effectively managing core facilities within the research enterprise. A framework is presented for organizing the questions, challenges, and opportunities facing core facilities and the academic units and institutions in which th...

  5. Department of Energy’s ARM Climate Research Facility External Data Center Operations Plan Located At Brookhaven National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Cialella, A. [Brookhaven National Lab. (BNL), Upton, NY (United States); Gregory, L. [Brookhaven National Lab. (BNL), Upton, NY (United States); Lazar, K. [Brookhaven National Lab. (BNL), Upton, NY (United States); Liang, M. [Brookhaven National Lab. (BNL), Upton, NY (United States); Ma, L. [Brookhaven National Lab. (BNL), Upton, NY (United States); Tilp, A. [Brookhaven National Lab. (BNL), Upton, NY (United States); Wagener, R. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-05-01

    The External Data Center (XDC) Operations Plan describes the activities performed to manage the XDC, located at Brookhaven National Laboratory (BNL), for the Department of Energy’s Atmospheric Radiation Measurement (ARM) Climate Research Facility. It includes all ARM infrastructure activities performed by the Data Management and Software Engineering Group (DMSE) at BNL. This plan establishes a baseline of expectation within the ARM Operations Management for the group managing the XDC.

  6. Research Facilities | Wind | NREL

    Science.gov (United States)

    Research Facilities Research Facilities NREL's state-of-the-art wind research facilities at the Research Facilities Photo of five men in hard hards observing the end of a turbine blade while it's being tested. Structural Research Facilities A photo of two people silhouetted against a computer simulation of

  7. Operation of spent fuel storage facilities

    International Nuclear Information System (INIS)

    1994-01-01

    This Safety Guide was prepared as part of the IAEA's programme on safety of spent fuel storage. This is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes key activities in the operation of spent fuel storage facilities. Section 3 lists the basic safety considerations for storage facility operation, the fundamental safety objectives being subcriticality, heat removal and radiation protection. Recommendations for organizing the management of a facility are contained in Section 4. Section 5 deals with aspects of training and qualification; Section 6 describes the phases of the commissioning of a spent fuel storage facility. Section 7 describes operational limits and conditions, while Section 8 deals with operating procedures and instructions. Section 9 deals with maintenance, testing, examination and inspection. Section 10 presents recommendations for radiation and environmental protection. Recommendations for the quality assurance (QA) system are presented in Section 11. Section 12 describes the aspects of safeguards and physical protection to be taken into account during operations; Section 13 gives guidance for decommissioning. 15 refs, 5 tabs

  8. Training manual for process operation and management of radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Shon, J. S.; Kim, K. J.; Ahn, S. J. [and others

    2004-12-01

    Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure.

  9. Training manual for process operation and management of radioactive waste treatment facility

    International Nuclear Information System (INIS)

    Shon, J. S.; Kim, K. J.; Ahn, S. J.

    2004-12-01

    Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure

  10. Sanford Underground Research Facility - The United State's Deep Underground Research Facility

    Science.gov (United States)

    Vardiman, D.

    2012-12-01

    The 2.5 km deep Sanford Underground Research Facility (SURF) is managed by the South Dakota Science and Technology Authority (SDSTA) at the former Homestake Mine site in Lead, South Dakota. The US Department of Energy currently supports the development of the facility using a phased approach for underground deployment of experiments as they obtain an advanced design stage. The geology of the Sanford Laboratory site has been studied during the 125 years of operations at the Homestake Mine and more recently as part of the preliminary geotechnical site investigations for the NSF's Deep Underground Science and Engineering Laboratory project. The overall geology at DUSEL is a well-defined stratigraphic sequence of schist and phyllites. The three major Proterozoic units encountered in the underground consist of interbedded schist, metasediments, and amphibolite schist which are crosscut by Tertiary rhyolite dikes. Preliminary geotechnical site investigations included drift mapping, borehole drilling, borehole televiewing, in-situ stress analysis, laboratory analysis of core, mapping and laser scanning of new excavations, modeling and analysis of all geotechnical information. The investigation was focused upon the determination if the proposed site rock mass could support the world's largest (66 meter diameter) deep underground excavation. While the DUSEL project has subsequently been significantly modified, these data are still available to provide a baseline of the ground conditions which may be judiciously extrapolated throughout the entire Proterozoic rock assemblage for future excavations. Recommendations for facility instrumentation and monitoring were included in the preliminary design of the DUSEL project design and include; single and multiple point extensometers, tape extensometers and convergence measurements (pins), load cells and pressure cells, smart cables, inclinometers/Tiltmeters, Piezometers, thermistors, seismographs and accelerometers, scanners (laser

  11. Historical Waste Retrieval and Clean-up Operations at Nuclear facility no.56, at the Cadarache Nuclear Research Centre

    International Nuclear Information System (INIS)

    Santucci, C.

    2008-01-01

    Among the different activities of the CEA research centre in Cadarache, located in the south of France, one of the most important involves cleaning, cleansing dismantling, decommissioning, and recovery of legacy wastes. This presentation will give an overview of the waste retrieval project from the historical interim storage facility called INB 56. The project is divided into three different sub-projects: the historical unpacked waste retrieval, the historical canister retrieval and the draining and clean-up of the spent fuel pools. All the described operations are conducted in accordance with the ALARA principle and the optimization of the waste categorization. The overall project, including the complete clean-up of the facility and its de-licensing, is due to end by 2020. The aim of this document is to outline the general ongoing historical waste retrieval operations and future projects on the INB 56 at the Cadarache research centre. In the final analysis, it can be seen that most of the waste is to be sent to the new CEDRA facility. Nevertheless one major goal of this project is to optimize the waste categorization and therefore to send the canisters to the ANDRA LLW site whenever possible. Two means will allow us to reach this goal: - The sorting out of un-packed waste in order to constitute a LLW canister - A wide range of measurements (gamma spectrometry, neutron measurement, tomography) in order to assess the exact nature of the contents in the historical canisters. Taking waste treatment and conditioning into account well in advance is a factor of prime importance that must be managed early in the elaboration of the decommissioning scenario. Precise knowledge of the physical and radiological inventories is of the utmost importance in defining the best waste pathway. Overall operations on the facility are due to end by 2020 including complete clean-up of the facility and its de-licensing

  12. Decommissioning Operations at the Cadarache Nuclear Research Center

    International Nuclear Information System (INIS)

    Gouhier, E.

    2008-01-01

    Among the different activities of the CEA research center of Cadarache, located in the south of France, one of the most important involves decommissioning. As old facilities close, decommissioning activity increases. This presentation will give an overview of the existing organization and the different ongoing decommissioning and cleanup operations on the site. We shall also present some of the new facilities under construction the purpose of which is to replace the decommissioned ones. Cadarache research center was created on October 14, 1959. Today, the activities of the research center are shared out among several technological R and D platforms, essentially devoted to nuclear energy (fission and fusion) Acting as a support to these R and D activities, the center of Cadarache has a platform of services which groups the auxiliary services required by the nuclear facilities and those necessary to the management of nuclear materials, waste, nuclear facility releases and decommissioning. Many old facilities have shut down in recent years (replaced by new facilities) and a whole decommissioning program is now underway involving the dismantling of nuclear reactors (Rapsodie, Harmonie), processing facilities (ATUE uranium treatment facility, LECA UO 2 facility) as well as waste treatment and storage facilities (INB37, INB 56. In conclusion: other dismantling and cleanup operations that are now underway in Cadarache include the following: - Waste treatment and storage facilities, - Historical VLLW and HLW storage facility, - Fissile material storage building, - Historical spent fuel storage facility. Thanks to the project organization: - Costs and risks on these projects can be reduced. - Engineers and technicians can easily move from one project to another. In some cases, when a new facility is under construction for the purpose of replacing a decommissioned one, some of the project team can integrate the new facility as members of the operation team. Today

  13. Gamma irradiation facility: Evaluation of operational modes

    International Nuclear Information System (INIS)

    Adesanmi, C.A.; Ali, M.S.; Shonowo, O.A.; Akueche, E.C.; Sadare, O.O.; Mustapha, T.K.; Yusuf, U.; Inyanda, A.K.

    2007-01-01

    The multipurpose Gamma Irradiation Facility (GIF) at the Nuclear Technology Centre (NTC), Sheda Science and Technology Complex (SHETSCO), Abuja, Nigeria is designed as a semi-commercial plant with facilities for research and development (R and D). The design takes into account the different needs of the various research applications which require a wide dose range, a variety of techniques, different product sizes, shapes, mass, volume, densities and types. Programmable doses are used for food irradiation (0.04 - 10 kGy), biological seed mutation breeding and sterile insect technique (STI) (0.01- 5 kGy) sterilization of medical, pharmaceutical and cosmetic products and packages (up to 25 kGy) and cross-linking of polymers (up to 100 kGy). The six different modes of operations (sample elevator, stationary, swiveling, 2-path inner lane and 2-path outer lane and 4-path line) were evaluated. The dose range, mass range and range of irradiation time practicable were established and advantages for radiation processing of food and industrial products were enumerated for the six modes of operations for the first time

  14. Operating experience of steam generator test facility

    International Nuclear Information System (INIS)

    Sureshkumar, V.A.; Madhusoodhanan, G.; Noushad, I.B.; Ellappan, T.R.; Nashine, B.K.; Sylvia, J.I.; Rajan, K.K.; Kalyanasundaram, P.; Vaidyanathan, G.

    2006-01-01

    Steam Generator (SG) is the vital component of a Fast Reactor. It houses both water at high pressure and sodium at low pressure separated by a tube wall. Any damage to this barrier initiates sodium water reaction that could badly affect the plant availability. Steam Generator Test Facility (SGTF) has been set up in Indira Gandhi Centre for Atomic Research (IGCAR) to test sodium heated once through steam generator of 19 tubes similar to the PFBR SG dimension and operating conditions. The facility is also planned as a test bed to assess improved designs of the auxiliary equipments used in Fast Breeder Reactors (FBR). The maximum power of the facility is 5.7 MWt. This rating is arrived at based on techno economic consideration. This paper covers the performance of various equipments in the system such as Electro magnetic pumps, Centrifugal sodium pump, in-sodium hydrogen meters, immersion heaters, and instrumentation and control systems. Experience in the system operation, minor modifications, overall safety performance, and highlights of the experiments carried out etc. are also brought out. (author)

  15. Cultivation of university students in radiology using research facilities at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Byung Chul [Nuclear Training and Education Center, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-09-15

    The purpose of present research is to offer a specialized educational opportunity for potential users, university students in radiology, by developing specific curriculum on site at KAERI, using HANARO research reactor and National radiation research facilities. The specific items of this research accomplished are: First, Development and operation of various curricula for specific research using HANARO and National radiation research facilities to provide university students with opportunities to use the facilities. Second, Operation of the experiment training programs for university students in radiology to foster next generation specialists. Third, through the on-site experiment training for students in radiology, support future potential experts of the radiation research fields, and broaden the base. A textbook and a teaching aid, a questionnaire have been developed to support the program. 714 university students have completed the courses for radiology experiment from 2006 to 2017. It is hoped that these experiments broaden public awareness and acceptance by the present and potential future utilization of the research reactor and national radiation research facilities, thereby bring positive impacts to policy making.

  16. Clinton P. Anderson Meson Physics Facility and its operational safety program

    International Nuclear Information System (INIS)

    Putnam, T.M.

    1975-01-01

    The Clinton P. Anderson Meson Physics Facility (LAMPF) at the Los Alamos Scientific Laboratory consists of/ (1) a medium-energy, high-intensity linear proton accelerator; (2) experimental areas designed to support a multidisciplined program of research and practical applications; and (3) support facilities for accelerator operations and the experimental program. The high-intensity primary and secondary beams at LAMPF and the varied research program create many interesting and challenging problems for the Health Physics staff. A brief overview of LAMPF is presented, and the Operational Safety Program is discussed, with emphasis on the radiological safety and health physics aspects

  17. The Sanford underground research facility at Homestake

    International Nuclear Information System (INIS)

    Heise, J.

    2014-01-01

    The former Homestake gold mine in Lead, South Dakota is being transformed into a dedicated laboratory to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e) and currently hosts three projects: the LUX dark matter experiment, the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment and the CUBED low-background counter. Plans for possible future experiments at SURF are well underway and include long baseline neutrino oscillation experiments, future dark matter experiments as well as nuclear astrophysics accelerators. Facility upgrades to accommodate some of these future projects have already started. SURF is a dedicated facility with significant expansion capability

  18. Decommissioning of the nuclear licensed facilities at the Fontenay aux Roses CEA Center; cleanup of nuclear licensed facility 57 and monitoring of operations and operating feedback

    International Nuclear Information System (INIS)

    Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.

    2008-01-01

    This is a summary of the program for the decommissioning of all the CEA Licensed Nuclear Facilities in Fontenay aux Roses. The particularity of this center is now it is located in a built-up area. It is presented like example the operations to clean up the equipment of the Nuclear Licensed Facility 57 (NLF 57). Due to the diversity of the research and development work carried out on the reprocessing of spent fuel in it, this installation is emblematic of many of the technical and organizational issues liable to be encountered in the final closure of nuclear facilities. It was developed a method applied to establish the multi-annual budget, monitor the progress of operations and integrate, as work continues, the operating feedback. (author)

  19. Operating procedures: Fusion Experiments Analysis Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lerche, R.A.; Carey, R.W.

    1984-03-20

    The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility.

  20. Operating procedures: Fusion Experiments Analysis Facility

    International Nuclear Information System (INIS)

    Lerche, R.A.; Carey, R.W.

    1984-01-01

    The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility

  1. Guide to research facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  2. Nuclear Safety Research and Facilities Department. Annual report 1999

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  3. Nuclear Safety Research and Facilities Department annual report 1997

    International Nuclear Information System (INIS)

    Majborn, B.; Aarkrog, A.; Brodersen, K.

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  4. Nuclear Safety Research and Facilities Department annual report 1998

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  5. Experimental facilities for Generation IV reactors research

    International Nuclear Information System (INIS)

    Krecanova, E.; Di Gabriele, F.; Berka, J.; Zychova, M.; Macak, J.; Vojacek, A.

    2013-06-01

    Centrum Vyzkumu Rez (CVR) is research and development Company situated in Czech Republic and member of the UJV group. One of its major fields is material research for Generation IV reactor concepts, especially supercritical water-cooled reactor (SCWR), very high temperature/gas-cooled fast reactor (VHTR/GFR) and lead-cooled fast reactor (LFR). The CVR is equipped by and is building unique experimental facilities which simulate the environment in the active zones of these reactor concepts and enable to pre-qualify and to select proper constructional materials for the most stressed components of the facility (cladding, vessel, piping). New infrastructure is founded within the Sustainable Energy project focused on implementation the Generation IV and fusion experimental facilities. The research of SCWR concept is divided to research and development of the constructional materials ensured by SuperCritical Water Loop (SCWL) and fuel components research on Fuel Qualification Test loop (SCWL-FQT). SCWL provides environment of the primary circuits of European SCWR, pressure 25 MPa, temperature 600 deg. C and its major purpose is to simulate behavior of the primary medium and candidate constructional materials. On-line monitoring system is included to collect the operational data relevant to experiment and its evaluation (pH, conductivity, chemical species concentration). SCWL-FQT is facility focused on the behavior of cladding material and fuel at the conditions of so-called preheater, the first pass of the medium through the fuel (in case of European SCWR concept). The conditions are 450 deg. C and 25 MPa. SCWL-FQT is unique facility enabling research of the shortened fuel rods. VHTR/GFR research covers material testing and also cleaning methods of the medium in primary circuit. The High Temperature Helium Loop (HTHL) enables exposure of materials and simulates the VHTR/GFR core environment to analyze the behavior of medium, especially in presence of organic compounds and

  6. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  7. Systems for aiding operators at university-owned research reactors in Japan

    International Nuclear Information System (INIS)

    Nishihara, H.; Kimura, Y.; Shibata, T.

    1984-01-01

    University-owned research reactors are operated for various purposes, and small disturbances may arise from various experimental facilities. Also not uniform are the technical levels of operators who range from supervised-students to reactor physicists. Considerable efforts are therefore devoted to the preventive maintainance. With these boundary conditions imposed, systems for aiding operators are designed at these research reactor facilities. (author)

  8. Accelerator based research facility as an inter university centre

    International Nuclear Information System (INIS)

    Mehta, G.K.

    1995-01-01

    15 UD pelletron has been operating as a user facility from July 1991. It is being utilised by a large number of universities and other institutions for research in basic Nuclear Physics, Materials Science, Atomic Physics, Radiobiology and Radiation Chemistry. There is an on-going programme for augmenting the accelerator facilities by injecting Pelletron beams into superconducting linear accelerator modules. Superconducting niobium resonator is being developed in Argonne National Laboratory as a joint collaborative effort. All other things such as cryostats, rf instrumentation, cryogenic distribution system, computer control etc are being done indigenously. Research facilities, augmentation plans and the research being conducted by the universities in various disciplines are described. (author)

  9. Control system of test and research facilities for nuclear energy industry

    International Nuclear Information System (INIS)

    1983-01-01

    IHI manufactures several kinds of test and research facilities used for research and development of new type power reactor and solidification system of high level radioactive liquid waste and safety research of light water reactor. These facilities are usually new type plants themselves, so that their control systems have to be designed individually for each plant with the basic conception. They have many operation modes because of their purposes of research and development, so the operation has to be automatized and requires the complicated sequence control system. In addition to these requirements, the detail design is hardly fixed on schedule and often modified during the initial start up period. Therefore, the computer control system was applied to these facilities with CRT display for man-machine communication earlier than to commercial power plants, because in the computer system the control logic is not hard wired but soft programmed and can be easily modified. In this paper, two typical computer control systems, one for PWR reflood test facility and another for mock-up test facility for solidification of liquid waste, are introduced. (author)

  10. Dosimetry and operation of irradiation facilities

    International Nuclear Information System (INIS)

    Vidal, P.E.

    1985-01-01

    The industrial use of ionizing radiation has required, from the very first, the measurement of delivered and absorbed doses; hence the necessity of providing dosimetric systems. Laboratories, scientists, industries and potential equipment manufacturers have all collaborated in this new field of activity. Dosimetric intercomparisons have been made by each industry at their own facilities and in collaboration with specialists, national organizations and the IAEA. Dosimetry has become a way of ensuring that treatment by irradiation has been carried out in accordance with the rules. It has become in effect assurance of quality. Routine dosimetry should determine a maximum and minimum dose. Numerous factors play a part in dosimetry. Industry is currently in possession of routine dosimetric systems that are sufficiently accurate, fairly easy to handle and reasonable in cost, thereby satisfying all the requirements of industry and the need for control. Dosimetry is important in the process of marketing irradiated products. The operator of an industrial irradiation facility bases his dosimetry on comparison with reference systems. Research aimed at simplifying the practice of routine dosimetry should be continued. New physical and chemical techniques will be incorporated into systems already in use. The introduction of microcomputers into the operation of radiation facilities has increased the value of dosimetry and made the conditions of treatment more widespread. Stress should be placed on research in several areas apart from reference systems, for example: dosimetric systems at temperatures from +8 deg. C to -45 deg. C, over the dose range 100 krad to a little more than 1 Mrad, liquids and fluidized solids carried at high speed through ducts, thin-film liquids circulating at a high flow rate, and various other problems. (author)

  11. Nuclear Safety Research and Facilities Department. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  12. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

    2000-01-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

  13. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

  14. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

  15. Nuclear Safety Research and Facilities department annual report 1996

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Heydorn, K.; Oelgaard, P.L.

    1997-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1996. The Department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 2 tabs., 28 ills

  16. Basic Research Firing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Basic Research Firing Facility is an indoor ballistic test facility that has recently transitioned from a customer-based facility to a dedicated basic research...

  17. BALU: Largest autoclave research facility in the world

    Directory of Open Access Journals (Sweden)

    Hakan Ucan

    2016-03-01

    Full Text Available Among the large-scale facilities operated at the Center for Lightweight-Production-Technology of the German Aerospace Center in Stade BALU is the world's largest research autoclave. With a loading length of 20m and a loading diameter of 5.8 m the main objective of the facility is the optimization of the curing process operated by components made of carbon fiber on an industrial scale. For this reason, a novel dynamic autoclaving control has been developed that is characterized by peripheral devices to expend the performance of the facility for differential applications, by sensing systems to detect the component state throughout the curing process and by a feedback system, which is capable to intervene into the running autoclave process.

  18. Facility approach to tokamak operation

    International Nuclear Information System (INIS)

    Edmonds, P.H.; Gabbard, W.A.

    1981-01-01

    In anticipation of the appearance of more advanced tokamaks and other fusion relevant experiments, program has been established at ORNL to systemically identify the requirements of an effective machine operations group. This program is presently applied to the ISX-B experiment. With its continuing development, it is expected to provide major support in the identification of potential problem areas and to assist in the generation of the necessary procedures for forthcoming devices. The present and future generations of large plasma devices will function as facilities, operated by an operations group as service to the plasma physicists and diagnosticians. The purpose of the program discussed here is to develop and to encourage an orderly transition to the facility-like style of operation

  19. Facilities for Research and Development of Medical Radioisotopes

    International Nuclear Information System (INIS)

    Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

    2003-03-01

    This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value

  20. Confirming competence of operators - A regulatory approach to fuel cycle facilities

    International Nuclear Information System (INIS)

    Vesely, M.; Sigetich, J.

    2013-01-01

    For the past 40 years the Canadian Nuclear Safety Commission (CNSC), formerly the Atomic Energy Control Board, has certified workers in nuclear facilities. The requirement for certified personnel has ensured that workers assigned to positions that have a direct impact on the safe operation of the facility are fully qualified to perform their duties. This certification regime is defined in the regulatory framework under which the CNSC operates. Traditionally, this certification regime has been applied to Reactor Operators, Shift Supervisors and Health Physicists in Nuclear Power Plants and research reactors as well as to Exposure Device Operators who use nuclear substances for the purposes of industrial radiography. Stemming from progress made in implementing risk-informed regulatory oversight activities as well as a formal suggestion from the International Atomic Energy Agency - International Regulatory Review Service (IRRS) conducted on the CNSC in 2009, a regulatory approach to confirming the competence of Operators at Fuel Cycle Facilities has been initiated by CNSC staff. In the first stage of the implementation of this new regulatory approach, the CNSC had Cameco Corporation implement a formal internal qualification programme for the UF6 Operators at its Port Hope Conversion Facility (PHCF) in Port Hope, Ontario. In the future, following a review of the results of the qualification programme at the PHCF, the CNSC staff will evaluate the need for the application of a similar regulatory approach to confirm the competence of the Operators at other Fuel Cycle Facilities in Canada. (authors)

  1. The Radiological Research Accelerator Facility. Progress report, December 1, 1993--November 30, 1994

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1994-04-01

    This document begins with a general description of the facility to include historical and up-to-date aspects of design and operation. A user's guide and a review of research using the facility follows. Next the accelerator utilization and operation and the development of the facilities is given. Personnel currently working at the facility are listed. Lastly, recent publications and literature cited are presented

  2. Hydrogen Infrastructure Testing and Research Facility Video (Text Version)

    Science.gov (United States)

    grid integration, continuous code improvement, fuel cell vehicle operation, and renewable hydrogen Systems Integration Facility or ESIF. Research projects including H2FIRST, component testing, hydrogen

  3. Research and development of power reactor technology supporting work, 3; Development of utility facility operation management technique

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    Demands on utility facilities for nuclear technology development are increasingly sophisticated and diversified. It is important to meet requirements of securing the reliability of utility supply and ensuring the safety of facility operation and maintenance by means of technical supporting, data supply and quick contingency responses. A New computer system to make practicable man-machine interface, real-time data acquisition and operation data centralization has been developed based on the knowledge. Obtained from data base information and operation experience for the purpose of operation efficiency and labor saving. (author).

  4. Establishment and Operation of User Facilities

    International Nuclear Information System (INIS)

    Kim, Kye Ryung; Park, B. S.; Lim, Y. K.; Lee, S. K.; Jung, J. P.

    2005-08-01

    The final goal of this project is to establish the proton beam user facility which can offer the suitable proton beam for the user's demand. In the first phase we developed the key technologies that were required for the establishment of 20MeV and 100MeV proton user facilities. The user's demand survey was also achieved, and the test user facility was established on the results of the demand survey. Using the test facility, the users performed their pilot studies. Now, we have finished the conceptual design for 20MeV proton user facility. During the first phase we performed the user's demand survey and produced many materials related to the proton beam utilizations in domestic or abroad. The survey results were reflected on the establishment of the test user facility and the conceptual design of 20MeV/100MeV proton beam user facilities. We have developed the key technologies which concern to beam energy control, flux control, uniform irradiation, dose and uniformity measurement, proton energy measurement, SOBP(Spread-out Bragg Peak) system using a rotating range modulator, and carried out the conceptual design of 20MeV proton user facility. The test user facility has been constructed and operated for both verifying the developed key technologies and performing the user's preliminary experiments. 45MeV low flux user facility was constructed in 2003 and has performed a lot of irradiation experiments. The development of 1.8MeV test user facility was completed. Also the low energy user facility that KAERI kept was upgraded and used for many users. Therefore, we provided our users with various beams. On the other hand, the following activities were carried out, such as, inviting the oversea researchers, giving support to users to use the beam in domestic and abroad, discussing the beam utilization technologies by visiting the foreign user facilities, etc

  5. High-Level Functional and Operational Requirements for the Advanced Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Charles Park

    2006-01-01

    This document describes the principal functional and operational requirements for the proposed Advanced Fuel Cycle Facility (AFCF). The AFCF is intended to be the world's foremost facility for nuclear fuel cycle research, technology development, and demonstration. The facility will also support the near-term mission to develop and demonstrate technology in support of fuel cycle needs identified by industry, and the long-term mission to retain and retain U.S. leadership in fuel cycle operations. The AFCF is essential to demonstrate a more proliferation-resistant fuel cycle and make long-term improvements in fuel cycle effectiveness, performance and economy

  6. Defense waste processing facility radioactive operations. Part 1 - operating experience

    International Nuclear Information System (INIS)

    Little, D.B.; Gee, J.T.; Barnes, W.M.

    1997-01-01

    The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation's first and the world's largest vitrification facility. Following a ten year construction program and a 3 year non-radioactive test program, DWPF began radioactive operations in March 1996. This paper presents the results of the first 9 months of radioactive operations. Topics include: operations of the remote processing equipment reliability, and decontamination facilities for the remote processing equipment. Key equipment discussed includes process pumps, telerobotic manipulators, infrared camera, Holledge trademark level gauges and in-cell (remote) cranes. Information is presented regarding equipment at the conclusion of the DWPF test program it also discussed, with special emphasis on agitator blades and cooling/heating coil wear. 3 refs., 4 figs

  7. Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations

    International Nuclear Information System (INIS)

    Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

    1997-01-01

    The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation's first and world's largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage

  8. Review of Regulatory Quality Assurance Requirements for the Operation of Nuclear R and D Facilities

    International Nuclear Information System (INIS)

    Kwon, Hyuk Il; Lim, Nam Jin

    2005-01-01

    Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation, including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently, nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/ contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. In this paper, the context of amended Atomic Energy laws were reviewed to confirm quality assurance measures and identify additional QA activities, if any, that is required by the amendment

  9. Decommissioning of small medical, industrial and research facilities

    International Nuclear Information System (INIS)

    2003-01-01

    Most of the technical literature on decommissioning addresses the regulatory, organizational, technical and other aspects for large facilities such as nuclear power plants, reprocessing plants and relatively large prototype, research and test reactors. There are, however, a much larger number of licensed users of radioactive material in the fields of medicine, research and industry. Most of these nuclear facilities are smaller in size and complexity and may present a lower radiological risk during their decommissioning. Such facilities are located at research establishments, biological and medical laboratories, universities, medical centres, and industrial and manufacturing premises. They are often operated by users who have not been trained or are unfamiliar with the decommissioning, waste management and associated safety aspects of these types of facility at the end of their operating lives. Also, for many small users of radioactive material such as radiation sources, nuclear applications are a small part of the overall business or process and, although the operating safety requirements may be adhered to, concern or responsibility may not go much beyond this. There is concern that even the minimum requirements of decommissioning may be disregarded, resulting in avoidable delays, risks and safety implications (e.g. a loss of radioactive material and a loss of all records). Incidents have occurred in which persons have been injured or put at risk. It is recognized that the strategies and specific requirements for small facilities may be much less onerous than for large ones such as nuclear power plants or fuel processing facilities, but many of the same principles apply. There has been considerable attention given to nuclear facilities and many IAEA publications are complementary to this report. This report, however, attempts to give specific guidance for small facilities. 'Small' in this report does not necessarily mean small in size but generally modest in terms

  10. Maintenance, repair and operation (MRO) of shutdown facilities

    International Nuclear Information System (INIS)

    Kenny, S.

    2006-01-01

    What level of maintenance does one apply to a shutdown facility? Well it depends on who you ask. Operations staff sees facilities that have completed their useful life cycle as a cost drain while Decommissioning staff sees this as the start of a new life cycle. Based on the decommissioning plan for the particular facility the building could complete another full life cycle while under decommissioning whether it is in storage with surveillance mode or under active decommissioning. This paper will explore how you maintain a facility and systems for many years after its useful life until final decommissioning is completed. When a building is declared redundant, who looks after it until the final decommissioning end state is achieved? At the AECL, Chalk River Labs site the safe shutdown and turnover process is one key element that initiates the decommissioning process. The real trick is orchestrating maintenance, repair and operation plans for a facility that has been poorly invested in during its last years of useful life cycle. To add to that usually shutdowns are prolonged for many years beyond the expected turnover period. During this presentation I will cover what AECL is doing to ensure that the facilities are maintained in a proper state until final decommissioning can be completed. All facilities or systems travel through the same life cycle, design, construction, commissioning, operation, shutdown and demolition. As we all know, nuclear facilities add one more interesting twist to this life cycle called Decommissioning that lands between shutdown and demolition. As a facility nears the shutdown phase, operations staff loose interest in the facility and stop investing in upgrades, repairs and maintenance but continue to invest and focus on maximizing operations. Facility maintenance standards produced by the International Facility Maintenance Association (IFMA) based on a survey done every year state that 2.2% of the total operating costs for the site should be

  11. Training and research reactor facility longevity extension program

    International Nuclear Information System (INIS)

    Carriveau, G.W.

    1991-01-01

    Since 1943, over 550 training and research reactors have been in operation. According to statistics from the International Atomic Energy Agency, ∼325 training and research reactors are currently in service. This total includes a wide variety of designs covering a range of power and research capabilities located virtually around the world. A program has been established at General Atomics (GA) that is dedicated to the support of extended longevity of training and research reactor facilities. Aspects of this program include the following: (1) new instrumentation and control systems; (2) improved and upgraded nuclear monitoring and control channels; (3) facility testing, repair and upgrade services that include (a) pool or tank integrity, (b) cooling system, and (c) water purification system; (4) fuel element testing procedures and replacement; (5) control rod drive rebuilding and upgrades; (6) control and monitoring system calibration and repair service; (7) training services, including reactor operations, maintenance, instrumentation calibration, and repair; and (8) expanded or new uses such as neutron radiography and autoradiography, isotope production, nuclear medicine, activation analysis, and material properties modification

  12. Scientific user facilities at Oak Ridge National Laboratory: New research capabilities and opportunities

    Science.gov (United States)

    Roberto, James

    2011-10-01

    Over the past decade, Oak Ridge National Laboratory (ORNL) has transformed its research infrastructure, particularly in the areas of neutron scattering, nanoscale science and technology, and high-performance computing. New facilities, including the Spallation Neutron Source, Center for Nanophase Materials Sciences, and Leadership Computing Facility, have been constructed that provide world-leading capabilities in neutron science, condensed matter and materials physics, and computational physics. In addition, many existing physics-related facilities have been upgraded with new capabilities, including new instruments and a high- intensity cold neutron source at the High Flux Isotope Reactor. These facilities are operated for the scientific community and are available to qualified users based on competitive peer-reviewed proposals. User facilities at ORNL currently welcome more than 2,500 researchers each year, mostly from universities. These facilities, many of which are unique in the world, will be reviewed including current and planned research capabilities, availability and operational performance, access procedures, and recent research results. Particular attention will be given to new neutron scattering capabilities, nanoscale science, and petascale simulation and modeling. In addition, user facilities provide a portal into ORNL that can enhance the development of research collaborations. The spectrum of partnership opportunities with ORNL will be described including collaborations, joint faculty, and graduate research and education.

  13. High level waste facilities - Continuing operation or orderly shutdown

    International Nuclear Information System (INIS)

    Decker, L.A.

    1998-04-01

    Two options for Environmental Impact Statement No action alternatives describe operation of the radioactive liquid waste facilities at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory. The first alternative describes continued operation of all facilities as planned and budgeted through 2020. Institutional control for 100 years would follow shutdown of operational facilities. Alternatively, the facilities would be shut down in an orderly fashion without completing planned activities. The facilities and associated operations are described. Remaining sodium bearing liquid waste will be converted to solid calcine in the New Waste Calcining Facility (NWCF) or will be left in the waste tanks. The calcine solids will be stored in the existing Calcine Solids Storage Facilities (CSSF). Regulatory and cost impacts are discussed

  14. Environmental Toxicology Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Fully-equipped facilities for environmental toxicology researchThe Environmental Toxicology Research Facility (ETRF) located in Vicksburg, MS provides over 8,200 ft...

  15. Applied research and service activities at the University of Missouri Research Reactor Facility (MURR)

    International Nuclear Information System (INIS)

    Alger, D.M.

    1987-01-01

    The University Of Missouri operates MURR to provide an intense source of neutron and gamma radiation for research and applications by experimenters from its four campuses and by experimenters from other universities, government and industry. The 10 MW reactor, which has been operating an average of 155 hours per week for the past eight years, produces thermal neutron fluxes up to 6-7x10 14 n/cm 2 -s in the central flux trap and beamport source fluxes of up to 1.2x10 14 n/cm 2 -s. The mission of the reactor facility, to promote research, education and service, is the same as the overall mission of the university and therefore, applied research and service supported by industrial firms have been welcomed. The university recognized after a few years of reactor operation that in order to build utilization, it would be necessary to develop in-house research programs including people, equipment and activity so that potential users could more easily and quickly obtain the results needed. Nine research areas have been developed to create a broadly based program to support the level of activity needed to justify the cost of operating the facility. Applied research and service generate financial support for about one-half of the annual budget. The applied and service programs provide strong motivation for university/industry association in addition to the income generated. (author)

  16. Shock Tube and Ballistic Range Facilities at NASA Ames Research Center

    Science.gov (United States)

    Grinstead, Jay H.; Wilder, Michael C.; Reda, Daniel C.; Cornelison, Charles J.; Cruden, Brett A.; Bogdanoff, David W.

    2010-01-01

    The Electric Arc Shock Tube (EAST) facility and the Hypervelocity Free Flight Aerodynamic Facility (HFFAF) at NASA Ames Research Center are described. These facilities have been in operation since the 1960s and have supported many NASA missions and technology development initiatives. The facilities have world-unique capabilities that enable experimental studies of real-gas aerothermal, gas dynamic, and kinetic phenomena of atmospheric entry.

  17. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    International Nuclear Information System (INIS)

    Adams, N

    2007-01-01

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

  18. Performance confirmation operation of water environment control facility

    International Nuclear Information System (INIS)

    Magome, Hirokatsu; Okada, Yuji; Tomita, Kenji; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Hanawa, Hiroshi; Kanno, Masaru; Sakuta, Yoshiyuki

    2015-09-01

    In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. The material irradiation test facility is used for IASCC study, and consists of mainly three equipments. This report described performance operating test of the water environmental control facilities for IASCC study carried out 2013 fiscal year. (author)

  19. Overview of the Life Science Glovebox (LSG) Facility and the Research Performed in the LSG

    Science.gov (United States)

    Cole, J. Michael; Young, Yancy

    2016-01-01

    The Life Science Glovebox (LSG) is a rack facility currently under development with a projected availability for International Space Station (ISS) utilization in the FY2018 timeframe. Development of the LSG is being managed by the Marshal Space Flight Center (MSFC) with support from Ames Research Center (ARC) and Johnson Space Center (JSC). The MSFC will continue management of LSG operations, payload integration, and sustaining following delivery to the ISS. The LSG will accommodate life science and technology investigations in a "workbench" type environment. The facility has a.Ii enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for handling Biohazard Level II and lower biological materials. This containment approach protects the crew from possible hazardous operations that take place inside the LSG work volume. Research investigations operating inside the LSG are provided approximately 15 cubic feet of enclosed work space, 350 watts of28Vdc and l IOVac power (combined), video and data recording, and real time downlink. These capabilities will make the LSG a highly utilized facility on ISS. The LSG will be used for biological studies including rodent research and cell biology. The LSG facility is operated by the Payloads Operations Integration Center at MSFC. Payloads may also operate remotely from different telescience centers located in the United States and different countries. The Investigative Payload Integration Manager (IPIM) is the focal to assist organizations that have payloads operating in the LSG facility. NASA provides an LSG qualification unit for payload developers to verify that their hardware is operating properly before actual operation on the ISS. This poster will provide an overview of the LSG facility and a synopsis of the research that will be accomplished in the LSG. The authors would like to acknowledge Ames Research Center, Johnson

  20. Facility design, installation and operation

    International Nuclear Information System (INIS)

    Fleischmann, A.W.

    1985-01-01

    Problems that may arise when considering the design, construction and use of a facility that could contain up to tens of petabecquerel of either cobalt-60 or caesium-137 are examined. The safe operation of an irradiation facility depends on an appreciation of the in built safety systems, adequate training of personnel and the existence of an emergency system

  1. Waste from decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    Massaut, V.

    2001-01-01

    Full text: Small nuclear facilities were often built for research or pilot purposes. It includes the research reactors of various types and various aims (physics research, nuclear research, nuclear weapons development, materials testing reactor, isotope production, pilot plant, etc.) as well as laboratories, hot cells and accelerators used for a broad spectrum of research or production purposes. These installations are characterized not only by their size (reduced footprint) but also, and even mostly, by the very diversified type of materials, products and isotopes handled within these facilities. This large variety can sometimes enhance the difficulties encountered for the dismantling of such facilities. The presence of materials like beryllium, graphite, lead, PCBs, sodium, sometimes in relatively large quantities, are also challenges to be faced by the dismantlers of such facilities, because these types of waste are either toxic or no solutions are readily available for their conditioning or long term disposal. The paper will review what is currently done in different small nuclear facilities, and what are the remaining problems and challenges for future dismantling and waste management. The question of whether Research and Development for waste handling methods and processes is needed is still pending. Even for the dismantling operation itself, important improvements can be brought in the fields of characterization, decontamination, remote handling, etc. by further developments and innovative systems. The way of funding such facilities decommissioning will be reviewed as well as the very difficult cost estimation for such facilities, often one-of-a-kind. The aspects of radioprotection optimization (ALARA principle) and classical operators safety will also be highlighted, as well as the potential solutions or improvements. In fact, small nuclear facilities encounter often, when dismantling, the same problems as the large nuclear power plants, but have in

  2. Fuel Supply Shutdown Facility Interim Operational Safety Requirements

    International Nuclear Information System (INIS)

    BENECKE, M.W.

    2000-01-01

    The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

  3. Detailed description of an SSAC at the facility level for research laboratory facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-08-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research laboratory facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  4. Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea

    International Nuclear Information System (INIS)

    Kwon, H.I.; Lim, N.J.

    2006-01-01

    Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the main law concerning the safety regulation of nuclear installations, and is supplemented by the Enforcement Decree and Enforcement Regulation of the Act. These Atomic Energy laws include provisions on the construction permission and the operation license of nuclear installations, such as nuclear power reactors, research reactors, nuclear ships, nuclear fuel fabrication facilities, spent fuel treatment facilities, etc. Regulatory requirements for the regulatory inspection and the safety measures for operation are also defined in the laws. The Notice of the MOST prescribes specific issues including regulatory requirements and technical standards, as entrusted by the AEA, the Decree and the Regulation. Detailed QA requirements for nuclear installations are specified differently, depending upon the type of facility. The guidelines for safety reviews and regulatory inspections are developed by the Korea Institute of Nuclear Safety (KINS), which is an exclusive organization for safety regulation of nuclear installations in Korea. In this paper, the context of the Atomic Energy laws were reviewed to confirm the

  5. Fuel conditioning facility electrorefiner cadmium vapor trap operation

    International Nuclear Information System (INIS)

    Vaden, D. E.

    1998-01-01

    Processing sodium-bonded spent nuclear fuel at the Fuel Conditioning Facility at Argonne National Laboratory-West involves an electrometallurgical process employing a molten LiCl-KCl salt covering a pool of molten cadmium. Previous research has shown that the cadmium dissolves in the salt as a gas, diffuses through the salt layer and vaporizes at the salt surface. This cadmium vapor condenses on cool surfaces, causing equipment operation and handling problems. Using a cadmium vapor trap to condense the cadmium vapors and reflux them back to the electrorefiner has mitigated equipment problems and improved electrorefiner operations

  6. Nuclear Safety Co-Ordination within Oak Ridge Operations Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, W. A.; Pryor, W. A. [Research and Development Division, United States Atomic Energy Commission, Oak Ridge, TN (United States)

    1966-05-15

    The Oak Ridge Operations Office of the USAEC has within its jurisdiction multiple contractors and facilities for research and for the production of fissile materials for the atomic energy programme. Among these facilities are gaseous diffusion plants for the production of {sup 235}U-enriched uranium hexafluoride, plants for the fabrication of special components and fuel for research and production reactors, and laboratories for pilot plant studies and basic research in nuclear technology. One research laboratory is also actively engaged in criticality experimental programmes and has been a major contributor of criticality data for safety applications. These diversified programmes include the processing, fabrication and transport of practically all forms and isotopic enrichments of uranium in quantities commensurate with both laboratory and volume production requirements. Consequently, adequate nuclear safety control with reasonable economy for operations of this magnitude demands not only co-ordination and liaison between contractor and USAEC staffs, but a continuing reappraisal of safety applications in light of the most advanced information. This report outlines the role of the Oak Ridge Operations Office in these pursuits and describes as examples some specific problems in which this office co-ordinated actions necessary for their resolution. Other examples are given of parametric and procedural applications in plant processes and fissile shipments emphasizing the use of recent experimental or calculated data. These examples involve the use of mass and geometric variables, neutron absorbers and moderation control. Departures from limits specified in existing nuclear safety guides are made to advantage in light of new data, special equipment design, contingencies and acceptable risks. (author)

  7. The reactor and cold neutron research facility at NIST

    Energy Technology Data Exchange (ETDEWEB)

    Prask, H J; Rowe, J M [Reactor Radiation Division, National Institute of Standards and Technology, Gaithersburg, MD (United States)

    1992-07-01

    The NIST Reactor (NBSR) is a 20 MW research reactor located at the Gaithersburg, MD site, and has been in operation since 1969. It services 26 thermal neutron facilities which are used for materials science, chemical analysis, nondestructive evaluation, neutron standards work, and irradiations. In 1987 the Department of Commerce and NIST began development of the CNRF - a $30M National Facility for cold neutron research -which will provide fifteen new experimental stations with capabilities currently unavailable in this country. As of May 1992, four of the planned seven guides and a cold port were installed, eight cold neutron experimental stations were operational, and the Call for Proposals for the second cycle of formally-reviewed guest-researcher experiments had been sent out. Some details of the performance of instrumentation are described, along with the proposed design of the new hydrogen cold source which will replace the present D{sub 2}O/H{sub 2}O ice cold source. (author)

  8. The reactor and cold neutron research facility at NIST

    International Nuclear Information System (INIS)

    Prask, H.J.; Rowe, J.M.

    1992-01-01

    The NIST Reactor (NBSR) is a 20 MW research reactor located at the Gaithersburg, MD site, and has been in operation since 1969. It services 26 thermal neutron facilities which are used for materials science, chemical analysis, nondestructive evaluation, neutron standards work, and irradiations. In 1987 the Department of Commerce and NIST began development of the CNRF - a $30M National Facility for cold neutron research -which will provide fifteen new experimental stations with capabilities currently unavailable in this country. As of May 1992, four of the planned seven guides and a cold port were installed, eight cold neutron experimental stations were operational, and the Call for Proposals for the second cycle of formally-reviewed guest-researcher experiments had been sent out. Some details of the performance of instrumentation are described, along with the proposed design of the new hydrogen cold source which will replace the present D 2 O/H 2 O ice cold source. (author)

  9. Radiological Research Accelerator Facility. Progress report, April 1-November 30, 1986

    International Nuclear Information System (INIS)

    1986-07-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology and radiological physics. The experiments run at RARAF are described, and center on neutron dosimetry, mutagenesis, and neutron-induced oncogenic transformations as well as survival of exposed cells. Accelerator utilization, operation, and development of facilities are reviewed

  10. Experience in using a research reactor for the training of power reactor operators

    International Nuclear Information System (INIS)

    Blotcky, A.J.; Arsenaut, L.J.

    1972-01-01

    A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

  11. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 5 tabs., 21 ills

  12. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L. [eds.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

  13. Materials and construction techniques for cryogenic wind tunnel facilities for instruction/research use

    Science.gov (United States)

    Morse, S. F.; Roper, A. T.

    1975-01-01

    The results of the cryogenic wind tunnel program conducted at NASA Langley Research Center are presented to provide a starting point for the design of an instructional/research wind tunnel facility. The advantages of the cryogenic concept are discussed, and operating envelopes for a representative facility are presented to indicate the range and mode of operation. Special attention is given to the design, construction and materials problems peculiar to cryogenic wind tunnels. The control system for operation of a cryogenic tunnel is considered, and a portion of a linearized mathematical model is developed for determining the tunnel dynamic characteristics.

  14. Remote operation and maintenance demonstration facility at ORNL

    International Nuclear Information System (INIS)

    Harvey, H.W.; Floyd, S.D.; Kuban, D.P.; Singletary, B.H.; Stradley, J.G.

    1978-01-01

    The Remote Operation and Maintenance Facility is a versatile facility arranged to mock up various hot cell configurations. Modular units of simulated shielding and viewing windows were built to provide flexibility in arrangement. The facility is fully equipped with hoists, manipulators, television, and other basic equipment and services necessary to provide capability for both remote operation and maintenance of several selected functional process equipment groups

  15. Operational and safety requirement of radiation facility

    International Nuclear Information System (INIS)

    Zulkafli Ghazali

    2007-01-01

    Gamma and electron irradiation facilities are the most common industrial sources of ionizing radiation. They have been used for medical, industrial and research purposes since the 1950s. Currently there are more than 160 gamma irradiation facilities and over 600 electron beam facilities in operation worldwide. These facilities are either used for the sterilization of medical and pharmaceutical products, the preservation of foodstuffs, polymer synthesis and modification, or the eradication of insect infestation. Irradiation with electron beam, gamma ray or ultra violet light can also destroy complex organic contaminants in both liquid and gaseous waste. EB systems are replacing traditional chemical sterilization methods in the medical supply industry. The ultra-violet curing facility, however, has found more industrial application in printing and furniture industries. Gamma and electron beam facilities produce very high dose rates during irradiation, and thus there is a potential of accidental exposure in the irradiation chamber which can be lethal within minutes. Although, the safety record of this industry has been relatively very good, there have been fatalities recorded in Italy (1975), Norway (1982), El Salvador (1989) and Israel (1990). Precautions against uncontrolled entry into irradiation chamber must therefore be taken. This is especially so in the case of gamma irradiation facilities those contain large amounts of radioactivity. If the mechanism for retracting the source is damaged, the source may remain exposed. This paper will, to certain extent, describe safety procedure and system being installed at ALURTRON, Nuclear Malaysia to eliminate accidental exposure of electron beam irradiation. (author)

  16. Procedures for economic distribution of radionuclides in research facilities

    International Nuclear Information System (INIS)

    Perry, N.A.

    1979-01-01

    A radionuclide accountability system for use in a research facility is described. It can be operated manually or adapted for computer use. All radionuclides are ordered, received, distributed and paid for by the Radiological Control Office who keep complete records of date of order, receipt, calibration use, transfer and/or disposal. Wipe leak tests, specific activity and lot number are also recorded. The procedure provides centralized total accountability records, including financial records, of all radionuclide orders, and the economic advantages of combined purchasing. The use of this system in two medical facilities has resulted in considerable financial savings in the first year of operation. (author)

  17. International Space Station Research and Facilities for Life Sciences

    Science.gov (United States)

    Robinson, Julie A.; Ruttley, Tara M.

    2009-01-01

    Assembly of the International Space Station is nearing completion in fall of 2010. Although assembly has been the primary objective of its first 11 years of operation, early science returns from the ISS have been growing at a steady pace. Laboratory facilities outfitting has increased dramatically 2008-2009 with the European Space Agency s Columbus and Japanese Aerospace Exploration Agency s Kibo scientific laboratories joining NASA s Destiny laboratory in orbit. In May 2009, the ISS Program met a major milestone with an increase in crew size from 3 to 6 crewmembers, thus greatly increasing the time available to perform on-orbit research. NASA will launch its remaining research facilities to occupy all 3 laboratories in fall 2009 and winter 2010. To date, early utilization of the US Operating Segment of the ISS has fielded nearly 200 experiments for hundreds of ground-based investigators supporting international and US partner research. With a specific focus on life sciences research, this paper will summarize the science accomplishments from early research aboard the ISS- both applied human research for exploration, and research on the effects of microgravity on life. We will also look ahead to the full capabilities for life sciences research when assembly of ISS is complete in 2010.

  18. Operational experiences and upgradation of waste management facilities Trombay, India

    International Nuclear Information System (INIS)

    Chander, Mahesh; Bodke, S.B.; Bansal, N.K.

    2001-01-01

    Full text: Waste Management Facilities Trombay provide services for the safe management of radioactive wastes generated from the operation of non power sources at Bhabha Atomic Research Centre, India. The paper describes in detail the current operational experience and facility upgradation by way of revamping of existing processes equipment and systems and augmentation of the facility by way of introducing latest processes and technologies to enhance the safety. Radioactive wastes are generated from the operation of research reactors, fuel fabrication, spent fuel reprocessing, research labs. manufacture of sealed sources and labeled compounds. Use of radiation sources in the field of medical, agriculture and industry also leads to generation of assorted solid waste and spent sealed radiation sources which require proper waste management. Waste Management Facilities Trombay comprise of Effluent Treatment Plant (ETP), Decontamination Centre (DC) and Radioactive Solid Waste Management Site (RSMS). Low level radioactive liquid effluents are received at ETP. Plant has 100 M 3 /day treatment capacity. Decontamination of liquid effluents is effected by chemical treatment method using co- precipitation as a process. Plant has 1800 M 3 of storage capacity. Chemical treatment system comprises of clarifloculator, static mixer and chemical feed tanks. Plant has concentrate management facility where chemical sludge is centrifuged to effect volume reduction of more that 15. Thickened sludge is immobilized in cement matrix. Decontamination Centre caters to the need of equipment decontamination from research reactors. Process used is ultrasonic chemical decontamination. Besides this DC provides services for decontamination of protective wears. Radioactive Solid Waste Management Site is responsible for the safe management of solid waste generated at various research reactors, plants, laboratories in Bhabha Atomic Research Centre. Spent sealed radiation sources are also stored

  19. Remote Operation and Maintenance Demonstration Facility at ORNL

    International Nuclear Information System (INIS)

    Harvey, H.W.; Floyd, S.D; Kuban, D.P.; Singletary, B.H.; Stradley, J.G.

    1978-01-01

    The Remote Operation and Maintenance Facility is a versatile facility arranged to mock-up various hot-cell configurations. Modular units of simulated shielding and viewing windows were built to provide flexibility in arrangement. The facility is fully equipped with hoists, manipulators, television, and the other basic equipment and services necessary to provide capability for both remote operation and maintenance of several selected functional process equipment groups. 6 figures

  20. Licence applications for low and intermediate level waste predisposal facilities: A manual for operators

    International Nuclear Information System (INIS)

    2009-07-01

    This publication covers all predisposal waste management facilities and practices for receipt, pretreatment (sorting, segregation, characterization), treatment, conditioning, internal relocation and storage of low and intermediate level radioactive waste, including disused sealed radioactive sources. The publication contains an Annex presenting the example of a safety assessment for a small radioactive waste storage facility. Facilities dealing with both short lived and long lived low and intermediate level waste generated from nuclear applications and from operation of small nuclear research reactors are included in the scope. Processing and storage facilities for high activity disused sealed sources and sealed sources containing long lived radionuclides are also covered. The publication does not cover facilities processing or storing radioactive waste from nuclear power plants or any other industrial scale nuclear fuel cycle facilities. Disposal facilities are excluded from the scope of this publication. Authorization process can be implemented in several stages, which may start at the site planning and the feasibility study stage and will continue through preliminary design, final design, commissioning, operation and decommissioning stages. This publication covers primarily the authorization needed to take the facility into operation

  1. Research Facility for Mechanical Press Closed Gap Adjuster

    Directory of Open Access Journals (Sweden)

    A. A. Ancifirov

    2016-01-01

    Full Text Available The article describes an example of the research facility for closed gap adjustment mechanism based on the KD2128 closed-die forging press. Its rated force with a servo drive used is 630kN. The servo drive consists of a motor with nominal power of 1.57kW and a frequency converter with power of 7.5kW, which has functions of the programmable logic controller.The article notes that such a facility is expedient and useful for practical classes on forging-andstamping machines at the BMSTU Department of «Technology processing by pressure» to demonstrate the capabilities of existing technological facility, learn a design of forging-andstamping machine units, solve the problems of automatic control, monitoring, and diagnostics in blank manufacturing.The article presents a detailed facility diagram of the closed gap adjustment mechanism and its photograph, describes the mechanism and its basic parameters, gives characteristics of the synchronous motor to drive the mechanism, reviews practical works, which the research facility may provide.Based on the four experiments the article estimates an efficiency of the research facilityuse under consideration, especially when modeling a servo motor shaft under the maximum load. The relevant diagrams confirm experimental results, namely: control current, angle of motor shaft and its speed versus time. Thus, upon the diagram analysis it can be noted that the research facility design allows providing kinematics and dynamics of the press closed gap adjuster.This article describes how to determine the closed gap adjusting accuracy of the press. Eight experiments have been conducted to evaluate a working out control signal to the linear movement of the press punch when using the research facility. It is noted that the linear positioning accuracy of the press punch reaches the hundredth parts of a millimeter of the adjustment value that is sufficient to achieve the required precision when performing operations such as

  2. Enhanced operator-training simulator for the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Schrader, F.D.; Swanson, C.D.

    1983-01-01

    The FFTF Plant Operator Training Simulator Facility has proven to be a valuable asset throughtout the testing, startup and early operational phases of the Fast Flux Test facility. However, limitations inherent in the existing simulation facility, increased emphasis on the required quality of operator training, and an expanded scope of applications (e.g., MNI development) justify an enhanced facility. Direct use of plant operators in the development of improved reactor control room displays and other man/machine interface equipment and procedures increases the credibility of proposed techniques and reported results. The FFTF Plant Operator Training Simulator provides a key element in this development program

  3. Large power supply facilities for fusion research

    International Nuclear Information System (INIS)

    Miyahara, Akira; Yamamoto, Mitsuyoshi.

    1976-01-01

    The authors had opportunities to manufacture and to operate two power supply facilities, that is, 125MVA computer controlled AC generator with a fly wheel for JIPP-T-2 stellerator in Institute of Plasma Physics, Nagoya University and 3MW trial superconductive homopolar DC generator to the Japan Society for Promotion of Machine Industry. The 125MVA fly-wheel generator can feed both 60MW (6kV x 10kA) DC power for toroidal coils and 20MW (0.5kV x 40kA) DC power for helical coils. The characteristic features are possibility of Bung-Bung control based on Pontrjagin's maximum principle, constant current control or constant voltage control for load coils, and cpu control for routine operation. The 3MW (150V-20000A) homopolar generator is the largest in the world as superconductive one, however, this capacity is not enough for nuclear fusion research. The problems of power supply facilities for large Tokamak devices are discussed

  4. Development and use of interactive displays in real-time ground support research facilities

    Science.gov (United States)

    Rhea, Donald C.; Hammons, Kvin R.; Malone, Jacqueline C.; Nesel, Michael C.

    1989-01-01

    The NASA Western Aeronautical Test Range (WATR) is one of the world's most advanced aeronautical research flight test support facilities. A variety of advanced and often unique real-time interactive displays has been developed for use in the mission control centers (MCC) to support research flight and ground testing. These dispalys consist of applications operating on systems described as real-time interactive graphics super workstations and real-time interactive PC/AT compatible workstations. This paper reviews these two types of workstations and the specific applications operating on each display system. The applications provide examples that demonstrate overall system capability applicable for use in other ground-based real-time research/test facilities.

  5. Filling the gaps in SCWR materials research: advanced nuclear corrosion research facilities in Hamilton

    International Nuclear Information System (INIS)

    Krausher, J.L.; Zheng, W.; Li, J.; Guzonas, D.; Botton, G.

    2011-01-01

    Research efforts on materials selection and development in support of the design of supercritical water-cooled reactors (SCWRs) have produced a considerable amount of data on corrosion, creep and other related properties. Summaries of the data on corrosion [1] and stress corrosion cracking [2] have recently been produced. As research on the SCWR advances, gaps and limitations in the published data are being identified. In terms of corrosion properties, these gaps can be seen in several areas, including: 1) the test environment, 2) the physical and chemical severity of the tests conducted as compared with likely reactor service/operating conditions, and 3) the test methods used. While some of these gaps can be filled readily using existing facilities, others require the availability of advanced test facilities for specific tests and assessments. In this paper, highlights of the new materials research facilities jointly established in Hamilton by CANMET Materials Technology Laboratory and McMaster University are presented. (author)

  6. Overview - Defense Waste Processing Facility Operating Experience

    International Nuclear Information System (INIS)

    Norton, M.R.

    2002-01-01

    The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the world's largest radioactive waste vitrification facility. Radioactive operations began in March 1996 and over 1,000 canisters have been produced. This paper presents an overview of the DWPF process and a summary of recent facility operations and process improvements. These process improvements include efforts to extend the life of the DWPF melter, projects to increase facility throughput, initiatives to reduce the quantity of wastewater generated, improved remote decontamination capabilities, and improvements to remote canyon equipment to extend equipment life span. This paper also includes a review of a melt rate improvement program conducted by Savannah River Technology Center personnel. This program involved identifying the factors that impacted melt rate, conducting small scale testing of proposed process changes and developing a cost effective implementation plan

  7. Facility Design and Health Management Program at the Sinnhuber Aquatic Research Laboratory.

    Science.gov (United States)

    Barton, Carrie L; Johnson, Eric W; Tanguay, Robert L

    2016-07-01

    The number of researchers and institutions moving to the utilization of zebrafish for biomedical research continues to increase because of the recognized advantages of this model. Numerous factors should be considered before building a new or retooling an existing facility. Design decisions will directly impact the management and maintenance costs. We and others have advocated for more rigorous approaches to zebrafish health management to support and protect an increasingly diverse portfolio of important research. The Sinnhuber Aquatic Research Laboratory (SARL) is located ∼3 miles from the main Oregon State University campus in Corvallis, Oregon. This facility supports several research programs that depend heavily on the use of adult, larval, and embryonic zebrafish. The new zebrafish facility of the SARL began operation in 2007 with a commitment to build and manage an efficient facility that diligently protects human and fish health. An important goal was to ensure that the facility was free of Pseudoloma neurophilia (Microsporidia), which is very common in zebrafish research facilities. We recognize that there are certain limitations in space, resources, and financial support that are institution dependent, but in this article, we describe the steps taken to build and manage an efficient specific pathogen-free facility.

  8. Status of the Holifield Heavy Ion Research Facility

    International Nuclear Information System (INIS)

    Martin, J.A.

    1978-01-01

    The Holifield Heavy Ion Research Facility presently operates the Oak Ridge Isochronous Cyclotron (ORIC). This accelerator provides heavy ions up to argon with energies useful for nuclear physics. The Phase I expansion of this facility, now a year away from completion, includes a 25-MV vertical folded tandem accelerator, beam transport and injection systems to use the ORIC as an energy booster, and additional experiment areas for the beams directly from the tandem. The tandem--cyclotron combination will provide heavy ions with energies up to 25 MeV/A for A 11 particles/sec. Building construction for the project is essentially complete. The accelerator manufacturer, National Electrostatics Corporation, has completed installation and testing of the 10-m-diam by 30-m-high accelerator pressure vessel and has begun installation of the accelerator systems. The accelerator has previously been assembled at the NEC plant and the digital control system operated without voltage on the column. Voltage tests are expected to begin in Oak Ridge in January 1979 with beam tests to begin in March. Completion of the project, including acceptance tests of the tandem and the beam injection system for ORIC is presently scheduled for November 15, 1979. Construction of Phase II for the facility wich will include a much larger booster cyclotron and additional research areas is expected to begin in 1982

  9. The ITER Neutral Beam Test Facility towards SPIDER operation

    Science.gov (United States)

    Toigo, V.; Dal Bello, S.; Gaio, E.; Luchetta, A.; Pasqualotto, R.; Zaccaria, P.; Bigi, M.; Chitarin, G.; Marcuzzi, D.; Pomaro, N.; Serianni, G.; Agostinetti, P.; Agostini, M.; Antoni, V.; Aprile, D.; Baltador, C.; Barbisan, M.; Battistella, M.; Boldrin, M.; Brombin, M.; Dalla Palma, M.; De Lorenzi, A.; Delogu, R.; De Muri, M.; Fellin, F.; Ferro, A.; Gambetta, G.; Grando, L.; Jain, P.; Maistrello, A.; Manduchi, G.; Marconato, N.; Pavei, M.; Peruzzo, S.; Pilan, N.; Pimazzoni, A.; Piovan, R.; Recchia, M.; Rizzolo, A.; Sartori, E.; Siragusa, M.; Spada, E.; Spagnolo, S.; Spolaore, M.; Taliercio, C.; Valente, M.; Veltri, P.; Zamengo, A.; Zaniol, B.; Zanotto, L.; Zaupa, M.; Boilson, D.; Graceffa, J.; Svensson, L.; Schunke, B.; Decamps, H.; Urbani, M.; Kushwah, M.; Chareyre, J.; Singh, M.; Bonicelli, T.; Agarici, G.; Garbuglia, A.; Masiello, A.; Paolucci, F.; Simon, M.; Bailly-Maitre, L.; Bragulat, E.; Gomez, G.; Gutierrez, D.; Mico, G.; Moreno, J.-F.; Pilard, V.; Chakraborty, A.; Baruah, U.; Rotti, C.; Patel, H.; Nagaraju, M. V.; Singh, N. P.; Patel, A.; Dhola, H.; Raval, B.; Fantz, U.; Fröschle, M.; Heinemann, B.; Kraus, W.; Nocentini, R.; Riedl, R.; Schiesko, L.; Wimmer, C.; Wünderlich, D.; Cavenago, M.; Croci, G.; Gorini, G.; Rebai, M.; Muraro, A.; Tardocchi, M.; Hemsworth, R.

    2017-08-01

    SPIDER is one of two projects of the ITER Neutral Beam Test Facility under construction in Padova, Italy, at the Consorzio RFX premises. It will have a 100 keV beam source with a full-size prototype of the radiofrequency ion source for the ITER neutral beam injector (NBI) and also, similar to the ITER diagnostic neutral beam, it is designed to operate with a pulse length of up to 3600 s, featuring an ITER-like magnetic filter field configuration (for high extraction of negative ions) and caesium oven (for high production of negative ions) layout as well as a wide set of diagnostics. These features will allow a reproduction of the ion source operation in ITER, which cannot be done in any other existing test facility. SPIDER realization is well advanced and the first operation is expected at the beginning of 2018, with the mission of achieving the ITER heating and diagnostic NBI ion source requirements and of improving its performance in terms of reliability and availability. This paper mainly focuses on the preparation of the first SPIDER operations—integration and testing of SPIDER components, completion and implementation of diagnostics and control and formulation of operation and research plan, based on a staged strategy.

  10. Annual report of intra-university joint-use facilities management and research for fiscal 1974

    International Nuclear Information System (INIS)

    1975-01-01

    Usage of RCNST's (Research Center for Nuclear Science and Technology) facilities by the University of Tokyo and results of the research works in fiscal 1974 are described. In the former are included facility operation, maintenance, etc. and frequency of usage. Comprising the fields of biology/medicine, chemistry/physics, engineering, materials, nuclear physics, etc., the research results are presented in individual summaries. (Mori, K.)

  11. Overview of the Microgravity Science Glovebox (MSG) Facility and the Research Performed in the MSG

    Science.gov (United States)

    Jordan, Lee

    2016-01-01

    The Microgravity Science Glovebox (MSG) is a rack facility aboard the International Space Station (ISS) designed for investigation handling. The MSG was built by the European Space Agency (ESA) which also provides sustaining engineering support for the facility. The MSG has been operating on the ISS since July 2002 and is currently located in the US Laboratory Module. The unique design of the facility allows it to accommodate science and technology investigations in a "workbench" type environment. The facility has an enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for small parts, particulates, fluids, and gases. This containment approach protects the crew from possible hazardous operations that take place inside the MSG work volume. Research investigations operating inside the MSG are provided a large 255 liter enclosed work space, 1000 watts of direct current power via a versatile supply interface (120, 28, plus or minus 12, and 5 volts direct current), 1000 watts of cooling capability, video and data recording and real time downlink, ground commanding capabilities, access to ISS Vacuum Exhaust and Vacuum Resource Systems, and gaseous nitrogen supply. These capabilities make the MSG one of the most utilized facilities on ISS. The MSG has been used for over 27,000 hours of scientific payload operations. MSG investigations involve research in cryogenic fluid management, fluid physics, spacecraft fire safety, materials science, combustion, plant growth, biological studies and life support technology. The MSG facility is operated by the Payloads Operations Integration Center at Marshall Space Flight Center. Payloads may also operate remotely from different telescience centers located in the United States and Europe. The Investigative Payload Integration Manager (IPIM) is the focal to assist organizations that have payloads operating in the MSG facility

  12. Operating manual for the Health Physics Research Reactor

    International Nuclear Information System (INIS)

    1985-11-01

    This manual is intended to serve as a guide in the operation and maintenance of the Health Physics Researh Reactor (HPRR) of the Health Physics Dosimetry Applications Research (DOSAR) Facility. It includes descriptions of the HPRR and of associated equipment such as the reactor positioning devises and the derrick. Procedures for routine operation of the HPRR are given in detail, and checklists for the various steps are provided where applicable. Emergency procedures are similarly covered, and maintenance schedules are outlined. Also, a bibliography of references giving more detailed information on the DOSAR Facility is included. Changes to this manual will be approved by at least two of the following senior staff members: (1) the Operations Division Director, (2) the Reactor Operations Department Head, (3) the Supervisor of Reactor Operations TSF-HPRR Areas. The master copy and the copy of the manual issued to the HPRR Operations Supervisor will always reflect the latest revision. 22 figs

  13. The operation of post-irradiation examination facility

    International Nuclear Information System (INIS)

    Kim, Eun Ka; Min, Duk Ki; Lee, Young Kil

    1994-12-01

    The operation of post-irradiation examination facility was performed as follow. HVAC and pool water treatment system were continuously operated, and radiation monitoring in PIE facility has been carried out to maintain the facility safely. Inspection of the fuel assembly (F02) transported from Kori Unit 1 was performed in pool, and fuel rods extracted from the fuel assembly (J44) of Kori Unit 2 NPP were examined in hot cell. A part of deteriorated pipe line of drinking water was exchanged for stainless steel pipe to prevent leaking accidents. Halon gas system was also installed in the exhausting blower room for fire fighting. And IAEA inspection camera for safeguard of nuclear materials was fixed at the wall in pool area. Radiation monitoring system were improved to display the area radioactive value at CRT monitor in health physics control room. And automatic check system for battery and emergency diesel generator was developed to measure the voltage and current of them. The performance test of oxide thickness measuring device installed in hot cell for irradiated fuel rod and improvement of the device were performed, and good measuring results using standard sample were obtained. The safeguard inspection of nuclear materials and operation inspection of the facility were carried out through the annual operation inspection, quarterly IAEA inspection and quality assurance auditing. 26 tabs., 43 figs., 14 refs. (Author) .new

  14. Estimation of radon concentration in various operating areas of a reprocessing facility

    International Nuclear Information System (INIS)

    Jayan, M.P.; Ashok Kumar, P.; Raman, Anand; Gopalakrishnan, R.K.

    2010-01-01

    This paper reports 222 Rn concentration of various operating areas of a reprocessing facility and also the U-processing area, measured using a microcontroller based Continuous Radon Monitor (CRM) built indigenously by Radiation Safety Systems Division, Bhabha Atomic Research Centre

  15. Considerations of Human Factors in the Design and Operation of Research Reactors

    International Nuclear Information System (INIS)

    Shokr, A.M.

    2015-01-01

    The feedback from the severe accidents occurred at nuclear power plants showed that safety of nuclear installations does not depend only on technical matters but also on human performance. Human errors can initiate an event or can make , by intervention, the event consequences worse. Human factors are of a particular importance for research reactors since the status of these facilities change frequently and the operators have an easy access to the reactor core and to the associated experimental facilities. This paper discusses the experience with human factors and their impact on the safety of research reactors and application of technical and administrative provisions to address these factors in the design and operation phases of research reactors for continuous improvements in safety and performance of these facilities

  16. A knowledge acquisition process to analyse operational problems in solid waste management facilities.

    Science.gov (United States)

    Dokas, Ioannis M; Panagiotakopoulos, Demetrios C

    2006-08-01

    The available expertise on managing and operating solid waste management (SWM) facilities varies among countries and among types of facilities. Few experts are willing to record their experience, while few researchers systematically investigate the chains of events that could trigger operational failures in a facility; expertise acquisition and dissemination, in SWM, is neither popular nor easy, despite the great need for it. This paper presents a knowledge acquisition process aimed at capturing, codifying and expanding reliable expertise and propagating it to non-experts. The knowledge engineer (KE), the person performing the acquisition, must identify the events (or causes) that could trigger a failure, determine whether a specific event could trigger more than one failure, and establish how various events are related among themselves and how they are linked to specific operational problems. The proposed process, which utilizes logic diagrams (fault trees) widely used in system safety and reliability analyses, was used for the analysis of 24 common landfill operational problems. The acquired knowledge led to the development of a web-based expert system (Landfill Operation Management Advisor, http://loma.civil.duth.gr), which estimates the occurrence possibility of operational problems, provides advice and suggests solutions.

  17. Integrated Urban Flood Analysis considering Optimal Operation of Flood Control Facilities in Urban Drainage Networks

    Science.gov (United States)

    Moon, Y. I.; Kim, M. S.; Choi, J. H.; Yuk, G. M.

    2017-12-01

    eavy rainfall has become a recent major cause of urban area flooding due to the climate change and urbanization. To prevent property damage along with casualties, a system which can alert and forecast urban flooding must be developed. Optimal performance of reducing flood damage can be expected of urban drainage facilities when operated in smaller rainfall events over extreme ones. Thus, the purpose of this study is to execute: A) flood forecasting system using runoff analysis based on short term rainfall; and B) flood warning system which operates based on the data from pump stations and rainwater storage in urban basins. In result of the analysis, it is shown that urban drainage facilities using short term rainfall forecasting data by radar will be more effective to reduce urban flood damage than using only the inflow data of the facility. Keywords: Heavy Rainfall, Urban Flood, Short-term Rainfall Forecasting, Optimal operating of urban drainage facilities. AcknowledgmentsThis research was supported by a grant (17AWMP-B066744-05) from Advanced Water Management Research Program (AWMP) funded by Ministry of Land, Infrastructure and Transport of Korean government.

  18. Identification of facility constraints that impact transportation operations

    International Nuclear Information System (INIS)

    Peterson, R.W.; Pope, R.B.

    1990-01-01

    As Federal waste Management Systems (FWMS) receiving facilities become available, the US Department of Energy (DOE) intends to begin accepting spent nuclear fuel from US utilities for eventual permanent disposal. Transporting the radioactive spent fuel to the repository will require development of a complex network of equipment, services, and operations personnel that will comprise the Transportation Operations System. This paper identifies and discusses, in a qualitative manner, the key reactor facility constraints that will eventually need to be assessed in detail on a site-specific basis to guide the development of the FWMS transportation cask fleet. This evaluation of constraints is needed to assess their impact on the size, composition, availability, and use of the cask fleet and to assist in the development of the transportation system support facilities such as a cask maintenance facility. Such assessment will also be needed to support decisions on modifying shipping facilities (i.e., reactors), identification and design of interface hardware, and on the designs of receiving facilities

  19. The Budapest research reactor as an advanced research facility for the early 21st century

    International Nuclear Information System (INIS)

    Vidovszky, I.

    2001-01-01

    The Budapest Research Reactor, Hungary's first nuclear facility was originally put into operation in 1959. The reactor serves for: basic and applied research, technological and commercial applications, education and training. The main goal of the reactor is to serve neutron research. This unique research possibility is used by a broad user community of Europe. Eight instruments for neutron scattering, radiography and activation analyses are already used, others (e.g. time of flight spectrometer, neutron reflectometer) are being installed. The majority of these instruments will get a much improved utilization when the cold neutron source is put into operation. In 1999 the Budapest Research Reactor was operated for 3129 full power hours in 14 periods. The normal operation period took 234 hours (starting Monday noon and finishing Thursday morning). The entire production for the year 1999 was 1302 MW days. This is a slightly reduced value, due to the installation of the cold neutron source. For the year 2000 a somewhat longer operation is foreseen (near to 4000 hours), as the cold neutron source will be operational. The operation of the reactor is foreseen at least up to the end of the first decade of the 21 st century. (author)

  20. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal, 1991

    International Nuclear Information System (INIS)

    1992-08-01

    The results of the joint researches by utilizing the facilities of JAERI in 1991 fiscal year were summarized, and this report was able to be completed. Many researchers in whole Japan took part in many themes, and the very significant results were obtained. Now this joint research has reached the great turnabout period. The reconstructed JRR-3M was offered for joint utilization since April, 1991, and the utilization for neutron diffraction and scattering increased largely. As for the ion irradiation facility in Takasaki Research Establishment, the partial operation will be started in the next year, and the joint utilization is expected to begin. Accompanying the diversification of the utilization of facilities, in order to properly meet the needs of users, the thorough revision of the system seems necessary. The number of research themes in 1991 was 222 cases. JRR-3M accomplished the joint utilization operation of 8 cycles as expected, but JRR-2 caused a trouble during 5th cycle, and the operation thereafter was canceled. In this book, 159 reports are collected. (K.I.)

  1. High Performance Computing Facility Operational Assessment 2015: Oak Ridge Leadership Computing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Barker, Ashley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bernholdt, David E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bland, Arthur S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Gary, Jeff D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Hack, James J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; McNally, Stephen T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Rogers, James H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Smith, Brian E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Straatsma, T. P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Sukumar, Sreenivas Rangan [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Thach, Kevin G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Tichenor, Suzy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Vazhkudai, Sudharshan S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Wells, Jack C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility

    2016-03-01

    Oak Ridge National Laboratory’s (ORNL’s) Leadership Computing Facility (OLCF) continues to surpass its operational target goals: supporting users; delivering fast, reliable systems; creating innovative solutions for high-performance computing (HPC) needs; and managing risks, safety, and security aspects associated with operating one of the most powerful computers in the world. The results can be seen in the cutting-edge science delivered by users and the praise from the research community. Calendar year (CY) 2015 was filled with outstanding operational results and accomplishments: a very high rating from users on overall satisfaction that ties the highest-ever mark set in CY 2014; the greatest number of core-hours delivered to research projects; the largest percentage of capability usage since the OLCF began tracking the metric in 2009; and success in delivering on the allocation of 60, 30, and 10% of core hours offered for the INCITE (Innovative and Novel Computational Impact on Theory and Experiment), ALCC (Advanced Scientific Computing Research Leadership Computing Challenge), and Director’s Discretionary programs, respectively. These accomplishments, coupled with the extremely high utilization rate, represent the fulfillment of the promise of Titan: maximum use by maximum-size simulations. The impact of all of these successes and more is reflected in the accomplishments of OLCF users, with publications this year in notable journals Nature, Nature Materials, Nature Chemistry, Nature Physics, Nature Climate Change, ACS Nano, Journal of the American Chemical Society, and Physical Review Letters, as well as many others. The achievements included in the 2015 OLCF Operational Assessment Report reflect first-ever or largest simulations in their communities; for example Titan enabled engineers in Los Angeles and the surrounding region to design and begin building improved critical infrastructure by enabling the highest-resolution Cybershake map for Southern

  2. Spent nuclear fuel project cold vacuum drying facility operations manual

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  3. A probabilistic risk assessment of the LLNL Plutonium Facility's evaluation basis fire operational accident. Revision 1

    International Nuclear Information System (INIS)

    Brumburgh, G.P.

    1995-01-01

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous programmatic activities involving plutonium to include device fabrication, development of improved and/or unique fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed in July 1994 to address operational safety and acceptable risk to employees, the public, government property, and the environmental. This paper outlines the PRA analysis of the Evaluation Basis Fire (EBF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

  4. Research on the Construction Management and Sustainable Development of Large-Scale Scientific Facilities in China

    Science.gov (United States)

    Guiquan, Xi; Lin, Cong; Xuehui, Jin

    2018-05-01

    As an important platform for scientific and technological development, large -scale scientific facilities are the cornerstone of technological innovation and a guarantee for economic and social development. Researching management of large-scale scientific facilities can play a key role in scientific research, sociology and key national strategy. This paper reviews the characteristics of large-scale scientific facilities, and summarizes development status of China's large-scale scientific facilities. At last, the construction, management, operation and evaluation of large-scale scientific facilities is analyzed from the perspective of sustainable development.

  5. The radiological research accelerator facility. Progress report, December 1, 1995--November 30, 1996

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1996-08-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) - formerly the Radiological Research Laboratory (RRL) - of Columbia University, and its operation is supported as a National Facility by the U.S. Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. RARAF was conceived in the mid-1960s by Drs. Victor P. Bond of Brookhaven National Laboratory (BNL) and Harald H. Rossi of Columbia University as a research resource dedicated to radiobiology and radiological physics and was officially established on January 1, 1967. The RARAF Van de Graaff accelerator originally served as the injector for the Cosmotron, a 2-GeV accelerator operated at BNL in the 1950s and early 1960s. The immediate aim was to provide a source of monoenergetic neutrons for studies in radiation biology, dosimetry, and microdosimetry. In other major projects the energetic ions produced were utilized directly. RARAF was located at BNL from 1967 until 1980, when it was dismantled and moved to the Nevis Laboratories of Columbia University, where it was then reassembled and returned to operation. This report contains the following information on RARAF: RARAF user's guide; scientific advisory committee; research using RARAF; accelerator utilization and operation; and development of the facilities

  6. Design, Fabrication, and Initial Operation of a Reusable Irradiation Facility

    International Nuclear Information System (INIS)

    Heatherly, D.W.; Thoms, K.R.; Siman-Tov, I.I.; Hurst, M.T.

    1999-01-01

    A Heavy-Section Steel Irradiation (HSSI) Program project, funded by the US Nuclear Regulatory Commission, was initiated at Oak Ridge National Laboratory to develop reusable materials irradiation facilities in which metallurgical specimens of reactor pressure vessel steels could be irradiated. As a consequence, two new, identical, reusable materials irradiation facilities have been designed, fabricated, installed, and are now operating at the Ford Nuclear Reactor at the University of Michigan. The facilities are referred to as the HSSI-IAR facilities with the individual facilities being designated as IAR-1 and IAR-2. This new and unique facility design requires no cutting or grinding operations to retrieve irradiated specimens, all capsule hardware is totally reusable, and materials transported from site to site are limited to specimens only. At the time of this letter report, the facilities have operated successfully for approximately 2500 effective full-power hours

  7. Establishment and operation of a photovoltaic cell test facility

    Energy Technology Data Exchange (ETDEWEB)

    Pearsall, N.M.; Forbes, I.

    1999-07-01

    This report describes the setting up of a test facility at the University of Northumbria. Details of the equipment specification and procurement are given, and the commissioning and initial operation of the facility, and the measurement procedures for I-V characteristics, spectral response measurements, optical scanning and test charges are outlined. The business plan for the test facility is discussed, and operating experience is reviewed in terms of publicity, services provided, and collaboration.

  8. Earthquake research for the safer siting of critical facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cluff, J.L. (ed.)

    1980-01-01

    The task of providing the necessities for living, such as adequate electrical power, water, and fuel, is becoming more complicated with time. Some of the facilities that provide these necessities would present potential hazards to the population if serious damage were to occur to them during earthquakes. Other facilities must remain operable immediately after an earthquake to provide life-support services to people who have been affected. The purpose of this report is to recommend research that will improve the information available to those who must decide where to site these critical facilities, and thereby mitigate the effects of the earthquake hazard. The term critical facility is used in this report to describe facilities that could seriously affect the public well-being through loss of life, large financial loss, or degradation of the environment if they were to fail. The term critical facility also is used to refer to facilities that, although they pose a limited hazard to the public, are considered critical because they must continue to function in the event of a disaster so that they can provide vital services.

  9. Radiological and the other safety aspects in the operation of electron beam facility

    International Nuclear Information System (INIS)

    Loterina, Roel Alamares

    2003-01-01

    The radiological safety aspects of the operation of an electron beam facility in general and the 3 MeV ALURTRON electron beam facility of the Malaysian Institute of Nuclear Technology Research (MINT) in particular were reviewed and evaluated. Evaluation was made based on existing records as well as actual monitoring around facility. Area monitoring results using TLDs are within permissible levels. The maximum reading of 7.29 mSv measured in year 2000 is very low as compared to the annual dose limit of 50 mSv/year. In general, the shielding for the installation is adequate and no significant radiation leakage were detected based on radiation survey results. However, measured radiation levels with a maximum of 1.9 mSv/h at the sampling ports easily exceed the limit of 25μSv/h. The facility is equipped with safety features, such as interlocked system, adequate shielding, engineered safety design of irradiation and accelerator rooms, and accessories such as conveyor system and product handling system. Warning lights and signals are adequately installed around the facility. Other identified hazards that may affect the operator, workers, and personnel were also evaluated based on previous records of monitoring. The ozone concentration levels with a maximum reading of 0.05 ppm measured in the environment of the facility are within the threshold limit value of 0.1 ppm. The measured noise levels at all locations around facility are generally below the maximum permissible level of 80dB. The ALURTRON has achieved a minimum safety requirement to warrant its full operation without relying on administrative controls and procedures to ensure safety in operation. (Auth.)

  10. Operating manual for the critical experiments facility

    International Nuclear Information System (INIS)

    1986-01-01

    The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written

  11. Operating manual for the critical experiments facility

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written.

  12. Spent Nuclear Fuel Project Cold Vacuum Drying Facility Operations Manual

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, (Cold Vacuum Drying Facility Design Requirements), Rev. 4. and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  13. Design and Validation of Control Room Upgrades Using a Research Simulator Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Jeffrey C. Joe; Julius J. Persensky

    2012-11-01

    Since 1981, the United States (U.S.) Nuclear Regulatory Commission (NRC) [1] requires a plant- specific simulator facility for use in training at U.S. nuclear power plants (NPPs). These training simulators are in near constant use for training and qualification of licensed NPP operators. In the early 1980s, the Halden Man-Machine Laboratory (HAMMLab) at the Halden Reactor Project (HRP) in Norway first built perhaps the most well known set of research simulators. The HRP offered a high- fidelity simulator facility in which the simulator is functionally linked to a specific plant but in which the human-machine interface (HMI) may differ from that found in the plant. As such, HAMMLab incorporated more advanced digital instrumentation and controls (I&C) than the plant, thereby giving it considerable interface flexibility that researchers took full advantage of when designing and validating different ways to upgrade NPP control rooms. Several U.S. partners—the U.S. NRC, the Electrical Power Research Institute (EPRI), Sandia National Laboratories, and Idaho National Laboratory (INL) – as well as international members of the HRP, have been working with HRP to run control room simulator studies. These studies, which use crews from Scandinavian plants, are used to determine crew behavior in a variety of normal and off-normal plant operations. The findings have ultimately been used to guide safety considerations at plants and to inform advanced HMI design—both for the regulator and in industry. Given the desire to use U.S. crews of licensed operators on a simulator of a U.S. NPP, there is a clear need for a research simulator facility in the U.S. There is no general-purpose reconfigurable research oriented control room simulator facility in the U.S. that can be used for a variety of studies, including the design and validation of control room upgrades.

  14. High Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — At NETL's High-Pressure Combustion Research Facility in Morgantown, WV, researchers can investigate new high-pressure, high-temperature hydrogen turbine combustion...

  15. Functional requirements for the man-vehicle systems research facility. [identifying and correcting human errors during flight simulation

    Science.gov (United States)

    Clement, W. F.; Allen, R. W.; Heffley, R. K.; Jewell, W. F.; Jex, H. R.; Mcruer, D. T.; Schulman, T. M.; Stapleford, R. L.

    1980-01-01

    The NASA Ames Research Center proposed a man-vehicle systems research facility to support flight simulation studies which are needed for identifying and correcting the sources of human error associated with current and future air carrier operations. The organization of research facility is reviewed and functional requirements and related priorities for the facility are recommended based on a review of potentially critical operational scenarios. Requirements are included for the experimenter's simulation control and data acquisition functions, as well as for the visual field, motion, sound, computation, crew station, and intercommunications subsystems. The related issues of functional fidelity and level of simulation are addressed, and specific criteria for quantitative assessment of various aspects of fidelity are offered. Recommendations for facility integration, checkout, and staffing are included.

  16. Concerning control of radiation exposure to workers in nuclear reactor facilities for testing and nuclear reactor facilities in research and development phase (fiscal 1987)

    International Nuclear Information System (INIS)

    1988-01-01

    A nuclear reactor operator is required by the Nuclear Reactor Control Law to ensure that the radiation dose to workers engaged in the operations of his nuclear reactor is controlled below the permissible exposure doses that are specified in notifications issued based on the Law. The present note briefly summarizes the data given in the Reports on Radiation Control, which have been submitted according to the Nuclear Reactor Control Law by the operators of nuclear reactor facilities for testing and those in the research and development phase, and the Reports on Control of Radiation Exposure to Workers submitted in accordance with the applicable administrative notices. According to these reports, the measured exposure to workers in 1987 were below the above-mentioned permissible exposure doses in all these nuclear facilities. The 1986 and 1987 measurements of radiation exposure dose to workers in nuclear reactor facilities for testing are tabulated. The measurements cover dose distribution among the facilities' personnel and workers of contractors. They also cover the total exposure dose for all workers in each of four plants operated under the Japan Atomic Energy Research Institute and the Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

  17. Optimum operation of a small power production facility

    Energy Technology Data Exchange (ETDEWEB)

    Capehart, B.L.; Mahoney, J.F.; Sivazlian, B.D.

    1983-09-01

    To help reduce the U.S.A.'s dependence on imported oil for electrical power generation, the 1978 National Energy Act established regulations to promote construction and operation of cogeneration and small power production facilities. Many of these facilities are presently under construction, with a great number planned. This paper examines the operation of a small power production facility with on-site generation and storage, on-site use, and connection to an electric utility grid system for the purpose of both selling excess power and buying power. It is assumed that the buying and selling price of electricity varies frequently during the day and that the relevant price and demand data may be accurately projected into the near future. With this system description, a mathematical model is formulated and solved by linear programming to obtain a series of periodic buy and sell decisions so as to maximize the profit from operating the small power production facility. Results are presented to illustrate the methodology for determining potential profits.

  18. LAMPF: a nuclear research facility

    International Nuclear Information System (INIS)

    Livingston, M.S.

    1977-09-01

    A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

  19. Lewis Research Center R and D Facilities

    Science.gov (United States)

    1991-01-01

    The NASA Lewis Research Center (LeRC) defines and develops advanced technology for high priority national needs. The work of the Center is directed toward new propulsion, power, and communications technologies for application to aeronautics and space, so that U.S. leadership in these areas is ensured. The end product is knowledge, usually in a report, that is made fully available to potential users--the aircraft engine industry, the energy industry, the automotive industry, the space industry, and other NASA centers. In addition to offices and laboratories for almost every kind of physical research in such fields as fluid mechanics, physics, materials, fuels, combustion, thermodynamics, lubrication, heat transfer, and electronics, LeRC has a variety of engineering test cells for experiments with components such as compressors, pumps, conductors, turbines, nozzles, and controls. A number of large facilities can simulate the operating environment for a complete system: altitude chambers for aircraft engines; large supersonic wind tunnels for advanced airframes and propulsion systems; space simulation chambers for electric rockets or spacecraft; and a 420-foot-deep zero-gravity facility for microgravity experiments. Some problems are amenable to detection and solution only in the complete system and at essentially full scale. By combining basic research in pertinent disciplines and generic technologies with applied research on components and complete systems, LeRC has become one of the most productive centers in its field in the world. This brochure describes a number of the facilities that provide LeRC with its exceptional capabilities.

  20. Magnetics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Magnetics Research Facility houses three Helmholtz coils that generate magnetic fields in three perpendicular directions to balance the earth's magnetic field....

  1. Cold neutron PGAA facility developments at university research reactors in the USA

    International Nuclear Information System (INIS)

    Uenlue, K.; Rios-Martinez, C.

    2005-01-01

    The PGAA applications can be enhanced by using subthermal neutrons, cold neutrons at university research reactors. Only two cold neutron beam facilities were developed at the U.S. university research reactors, namely at Cornell University and the University of Texas at Austin. Both facilities used mesitylene moderator. The mesitylene moderator in the Cornell Cold Neutron Beam Facility (CNBF) was cooled by a helium cryorefrigerator via copper cold fingers to maintain the moderator below 30 K at full power reactor operation. Texas Cold Neutron Source (TCNS) also uses mesitylene moderator that is cooled by a cryorefrigerator via a neon thermosiphon. The operation of the TCNS is based on a helium cryorefrigerator, which liquefies neon gas in a 3-m long thermosiphon. The thermosiphon cools and maintains mesitylene moderator at about 30 K in a chamber. Neutrons streaming through the mesitylene chamber are moderated and thus reduce their energy to produce a cold neutron distribution. (author)

  2. The International Facility for Antiproton and Ion Research FAIR

    International Nuclear Information System (INIS)

    Gutbrod, H. H.

    2008-01-01

    The proposed project FAIR (Facility for Antiproton and Ion Research) is an international accelerator facility of the next generation and will be built as a new company FAIR GmbH next to the site of GSI. About 15 countries have expressed their intention to become shareholders. FAIR builds on the experience and technological developments already made at the existing GSI facility, and at the FAIR partner institutes world wide and incorporates new technological concepts. At its heart is a double ring facility with a circumference of 1100 meters. A system of cooler-storage rings for effective beam cooling at high energies and various experimental halls will be connected to the facility. The existing GSI accelerators - together with the planned proton-linac - serve as injector for the new facility. The double-ring synchrotron will provide ion beams of unprecedented intensities as well as of considerably increased energy. Thereby intense beams of secondary beams - unstable nuclei or antiprotons - can be produced. The system of storage-cooler rings allows the quality of these secondary beams - their energy spread and emittance - to be drastically improved. Moreover, in connection with the double ring synchrotron, an efficient parallel operation of up to four scientific programs can be realized at a time. The project is based on many technological innovations, the most important of which are five beam properties: Highest Beam Intensities, Brilliant Beam Quality, Higher Beam Energies, Highest Beam Power, Parallel Operation

  3. 26 CFR 1.132-7 - Employer-operated eating facilities.

    Science.gov (United States)

    2010-04-01

    ... Employer-operated eating facilities. (a) In general—(1) Condition for exclusion—(i) General rule. The value... dining room or cafeteria in which meals are served is treated as a separate eating facility, whether each such dining room or cafeteria has its own kitchen or other food-preparation area. (2) Employer-operated...

  4. A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

    International Nuclear Information System (INIS)

    Brumburgh, G.

    1994-01-01

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

  5. Geodynamics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This GSL facility has evolved over the last three decades to support survivability and protective structures research. Experimental devices include three gas-driven...

  6. Operation manual for the INEL on-line mass-separator facility

    International Nuclear Information System (INIS)

    Anderl, R.A.

    1984-06-01

    This report is an operation manual for an on-line mass-separator facility which is located in Building 661 at the Test Reactor Area of the Idaho National Engineering Laboratory. The facility provides mass-separated sources of short-lived fission-product radionuclides whose decay properties can be studied using a variety of nuclear spectroscopic techniques. This facility is unique in that it utilizes the gas-jet technique to transport fission products from a 252 Cf source located in a hot cell to the ion source of the mass separator. This document includes the following: (a) a detailed description of the facility, (b) identification of equipment hazards and safety controls, (c) detailed operating procedures for startup, continuous operation and shutdown, (d) operating procedures for the californium hot cell, and (e) an operator's manual for the automated moving tape collector/data acquisition system. 7 references, 16 figures, 8 tables

  7. Operational safety analysis of the Olkiluoto encapsulation plant and disposal facility

    International Nuclear Information System (INIS)

    Rossi, J.; Suolanen, V.

    2012-11-01

    Radiation doses for workers of the facility, for inhabitants in the environment and for terrestrial ecosystem possibly caused by the encapsulation and disposal facilities to be built at Olkiluoto during its operation were considered in the study. The study covers both the normal operation of the plant and some hypothetical incidents and accidents. Release through the ventilation stack is assumed to be filtered both in normal operation and in hypothetical abnormal fault and accident cases. In addition the results for unfiltered releases are also presented. This research is limited to the deterministic analysis. During about 30 operation years of our four nuclear power plant units there have been found 58 broken fuel pins. Roughly estimating there has been one fuel leakage per year in a facility (includes two units). Based on this and adopting a conservative approach, it is estimated that one fuel pin per year could leak in normal operation during encapsulation process. The release magnitude in incidents and accidents is based on the event chains, which lead to loss of fuel pin tightness followed by a discharge of radionuclides into the handling space and to some degree to the atmosphere through the ventilation stack equipped with redundant filters. The most exposed group of inhabitants is conservatively assumed to live at the distance of 200 meters from the encapsulation and disposal plant and it will receive the largest doses in most dispersion conditions. The dose value to a member of the most exposed group was calculated on the basis of the weather data in such a way that greater dose than obtained here is caused only in 0.5 percent of dispersion conditions. The results obtained indicate that during normal operation the doses to workers remain small and the dose to the member of the most exposed group is less than 0.001 mSv per year. In the case of hypothetical fault and accident releases the offsite doses do not exceed either the limit values set by the safety

  8. Report of the research results with joint-use facilities in fiscal year 1977

    International Nuclear Information System (INIS)

    1978-01-01

    In the Nuclear Engineering Research Laboratory, the University of Tokyo, fast neutron source reactor 'Yayoi', linac and fusion-reactor blanket facility are jointly used by educational institutions. Research results from the joint uses of the facilities in fiscal 1977 are presented in individual summaries: (on-pile) irradiation, reactor physics and engineering, etc., (off-pile) equipment and component techniques, etc., (linac) operation, etc., with these joint uses, unique works are intended in resonable way. (Mori, K.)

  9. The Sondrestrom Research Facility All-sky Imagers

    Science.gov (United States)

    Kendall, E. A.; Grill, M.; Gudmundsson, E.; Stromme, A.

    2010-12-01

    The Sondrestrom Upper Atmospheric Research Facility is located near Kangerlussuaq, Greenland, just north of the Arctic Circle and 100 km inland from the west coast of Greenland. The facility is operated by SRI International in Menlo Park, California, under the auspices of the U.S. National Science Foundation. Operating in Greenland since 1983, the Sondrestrom facility is host to more than 20 instruments, the majority of which provide unique and complementary information about the arctic upper atmosphere. Together these instruments advance our knowledge of upper atmospheric physics and determine how the tenuous neutral gas interacts with the charged space plasma environment. The suite of instrumentation supports many disciplines of research - from plate tectonics to auroral physics and space weather. The Sondrestrom facility has recently acquired two new all-sky imagers. In this paper, we present images from both new imagers, placing them in context with other instruments at the site and detailing to the community how to gain access to this new data set. The first new camera replaces the intensified auroral system which has been on site for nearly three decades. This new all-sky imager (ASI), designed and assembled by Keo Scientific Ltd., employs a medium format 180° fisheye lens coupled to a set of five 3-inch narrowband interference filters. The current filter suite allows operation at the following wavelengths: 750 nm, 557.7 nm, 777.4 nm, 630.0 nm, and 732/3 nm. Monochromatic images from the ASI are acquired at a specific filter and integration time as determined by a unique configuration file. Integrations as short as 0.5 sec can be commanded for exceptionally bright features. Preview images are posted to the internet in near real-time, with final images posted weeks later. While images are continuously collected in a "patrol mode," users can request special collection sequences for targeted experiments. The second new imager installed at the Sondrestrom

  10. Accelerator-based research facility of UGC as an inter-university centre

    International Nuclear Information System (INIS)

    Mehta, G.K.

    1994-01-01

    A 15-UD Pelletron has been operating as a users facility from July 1991. It is being utilised by a large number of universities and other institutions for research in basic nuclear physics, materials science, atomic physics, radiobiology and radiation chemistry. There is an on-going programme for augmenting the accelerator facilities by injecting Pelletron beams into superconducting linear accelerator modules. Superconducting niobium resonators are being developed at Argonne National Laboratory as a joint collaborative effort. All other things such as cryostat, rf-instrumentation, cryogene distribution system, computer control etc. are being done indigenously. Research possibilities are described. (author). 6 refs., 4 figs

  11. Study of the Relevance of the Quality of Care, Operating Efficiency and Inefficient Quality Competition of Senior Care Facilities.

    Science.gov (United States)

    Lin, Jwu-Rong; Chen, Ching-Yu; Peng, Tso-Kwei

    2017-09-11

    The purpose of this research is to examine the relation between operating efficiency and the quality of care of senior care facilities. We designed a data envelopment analysis, combining epsilon-based measure and metafrontier efficiency analyses to estimate the operating efficiency for senior care facilities, followed by an iterative seemingly unrelated regression to evaluate the relation between the quality of care and operating efficiency. In the empirical studies, Taiwan census data was utilized and findings include the following: Despite the greater operating scale of the general type of senior care facilities, their average metafrontier technical efficiency is inferior to that of nursing homes. We adopted senior care facility accreditation results from Taiwan as a variable to represent the quality of care and examined the relation of accreditation results and operating efficiency. We found that the quality of care of general senior care facilities is negatively related to operating efficiency; however, for nursing homes, the relationship is not significant. Our findings show that facilities invest more in input resources to obtain better ratings in the accreditation report. Operating efficiency, however, does not improve. Quality competition in the industry in Taiwan is inefficient, especially for general senior care facilities.

  12. The Design of HVAC System in the Conventional Facility of Proton Accelerator Research Center

    International Nuclear Information System (INIS)

    Jeon, G. P.; Kim, J. Y.; Choi, B. H.

    2007-01-01

    The HVAC systems for conventional facility of Proton Accelerator Research Center consist of 3 systems : accelerator building HVAC system, beam application building HVAC system and miscellaneous HVAC system. We designed accelerator building HVAC system and beam application research area HVAC system in the conventional facilities of Proton Accelerator research center. Accelerator building HVAC system is divided into accelerator tunnel area, klystron area, klystron gallery area, accelerator assembly area. Also, Beam application research area HVAC system is divided into those of beam experimental hall, accelerator control area, beam application research area and Ion beam application building. In this paper, We described system design requirements and explained system configuration for each systems. We presented operation scenario of HVAC system in the Conventional Facility of Proton Accelerator Research Center

  13. Survey of tritium wastes and effluents in near-term fusion-research facilities

    International Nuclear Information System (INIS)

    Bickford, W.E.; Dingee, D.A.; Willingham, C.E.

    1981-08-01

    The use of tritium control technology in near-term research facilities has been studied for both the magnetic and inertial confinement fusion programs. This study focused on routine generation of tritium wastes and effluents, with little referene to accidents or facility decommissioning. This report serves as an independent review of the effectiveness of planned control technology and radiological hazards associated with operation. The facilities examined for the magnetic fusion program included Fusion Materials Irradiation Testing Facility (FMIT), Tritium Systems Test Assembly (TSTA), and Tokamak Fusion Test Reactor (TFTR) in the magnetic fusion program, while NOVA and Antares facilities were examined for the inertial confinement program

  14. Environmental assessment of the Carlsbad Environmental Monitoring and Research Center Facility

    International Nuclear Information System (INIS)

    1995-10-01

    This Environmental Assessment has been prepared to determine if the Carlsbad Environmental Monitoring and Research Center (the Center), or its alternatives would have significant environmental impacts that must be analyzed in an Environmental Impact Statement. DOE's proposed action is to continue funding the Center. While DOE is not funding construction of the planned Center facility, operation of that facility is dependent upon continued funding. To implement the proposed action, the Center would initially construct a facility of approximately 2,300 square meters (25,000 square feet). The Phase 1 laboratory facilities and parking lot will occupy approximately 1.2 hectares (3 acres) of approximately 8.9 hectares (22 acres) of land which were donated to New Mexico State University (NMSU) for this purpose. The facility would contain laboratories to analyze chemical and radioactive materials typical of potential contaminants that could occur in the environment in the vicinity of the DOE Waste Isolation Pilot Plant (WIPP) site or other locations. The facility also would have bioassay facilities to measure radionuclide levels in the general population and in employees of the WIPP. Operation of the Center would meet the DOE requirement for independent monitoring and assessment of environmental impacts associated with the planned disposal of transuranic waste at the WIPP

  15. Environmental assessment of the Carlsbad Environmental Monitoring and Research Center Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This Environmental Assessment has been prepared to determine if the Carlsbad Environmental Monitoring and Research Center (the Center), or its alternatives would have significant environmental impacts that must be analyzed in an Environmental Impact Statement. DOE`s proposed action is to continue funding the Center. While DOE is not funding construction of the planned Center facility, operation of that facility is dependent upon continued funding. To implement the proposed action, the Center would initially construct a facility of approximately 2,300 square meters (25,000 square feet). The Phase 1 laboratory facilities and parking lot will occupy approximately 1.2 hectares (3 acres) of approximately 8.9 hectares (22 acres) of land which were donated to New Mexico State University (NMSU) for this purpose. The facility would contain laboratories to analyze chemical and radioactive materials typical of potential contaminants that could occur in the environment in the vicinity of the DOE Waste Isolation Pilot Plant (WIPP) site or other locations. The facility also would have bioassay facilities to measure radionuclide levels in the general population and in employees of the WIPP. Operation of the Center would meet the DOE requirement for independent monitoring and assessment of environmental impacts associated with the planned disposal of transuranic waste at the WIPP.

  16. French en engineering and operation rules for plutonium facilities

    International Nuclear Information System (INIS)

    Bertolotti, G.; Drain, F.; Dubois, G.; Monnatte, J.; Mathieu, P.

    1998-01-01

    COGEMA is operating large size purifying and conditioning plutonium facilities at LA HAGUE and MOX fuels fabrication plant at Marcoule. A high safety standard is recognised for these facilities. It is mainly based on : - prevention of spreading of radioactive materials to workers and environment by physical barriers ensuring static containment and by a cascade of pressure differentials ensuring dynamic containment, - radiation shielding and remote controlled processes ensuring very low dose to workers, - prevention of criticality accident by criticality control methods and double contingency principle, - prevention of fire risks by control of ignition sources, adequate management of combustible materials, physical separation between zones where there is a risk of fire and the remainder of the facility. The facilities are operated while respecting safety requirements as described in the General Operating Rules. The equipment involved in safety functions are monitored and periodically checked. Continuous improvement by incorporation of feed back of safety experience results in: - effective decrease of exposure to operating staff; - reduction of solid waste, liquid and gaseous effluents; - no significant incident recorded. (author)

  17. On exposure of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The Law for Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1988 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the exposure of workers was below the permissible exposure dose in 1988 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of Japan Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

  18. Introducing COSS: A new and unique oil spill research facility

    International Nuclear Information System (INIS)

    Kitchen, R. B.; Bonner, J. S.; Autenrieth, R. L.; Donnelly, K. C.; Ernest, A. N. S.

    1997-01-01

    A new oil spill research facility in Corpus Christi, Texas began operation in April 1997 to address the appropriate use, application and effectiveness of chemical, physical and biological oil spill response agents. The Coastal Oil Spill Simulation (COSS) facility consists of nine meso scale wave tanks and will offer to science and industry a unique opportunity to spill oil in a controlled environment and to study fate, transport and remediation of oil releases in simulated coastal, intertidal, lagunal, channel and porous media. 1 ref

  19. Design strategies for the International Space University's variable gravity research facility

    Science.gov (United States)

    Bailey, Sheila G.; Chiaramonte, Francis P.; Davidian, Kenneth J.

    1990-01-01

    A variable gravity research facility named 'Newton' was designed by 58 students from 13 countries at the International Space University's 1989 summer session at the Universite Louis Pasteur, Strasbourge, France. The project was comprehensive in scope, including a political and legal foundation for international cooperation, development and financing; technical, science and engineering issues; architectural design; plausible schedules; and operations, crew issues and maintenance. Since log-term exposure to zero gravity is known to be harmful to the human body, the main goal was to design a unique variable gravity research facility which would find a practical solution to this problem, permitting a manned mission to Mars. The facility would not duplicate other space-based facilities and would provide the flexibility for examining a number of gravity levels, including lunar and Martian gravities. Major design alternatives included a truss versus a tether based system which also involved the question of docking while spinning or despinning to dock. These design issues are described. The relative advantages or disadvantages are discussed, including comments on the necessary research and technology development required for each.

  20. Report on operation of nuclear facilities in 1991

    International Nuclear Information System (INIS)

    1992-06-01

    The Slovenian Nuclear Safety Administration (SNSA) prepared a report on nuclear safety in the republic of Slovenia in 1991 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into three thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia and the operation of nuclear facilities around the world.

  1. A test matrix sequencer for research test facility automation

    Science.gov (United States)

    Mccartney, Timothy P.; Emery, Edward F.

    1990-01-01

    The hardware and software configuration of a Test Matrix Sequencer, a general purpose test matrix profiler that was developed for research test facility automation at the NASA Lewis Research Center, is described. The system provides set points to controllers and contact closures to data systems during the course of a test. The Test Matrix Sequencer consists of a microprocessor controlled system which is operated from a personal computer. The software program, which is the main element of the overall system is interactive and menu driven with pop-up windows and help screens. Analog and digital input/output channels can be controlled from a personal computer using the software program. The Test Matrix Sequencer provides more efficient use of aeronautics test facilities by automating repetitive tasks that were once done manually.

  2. Operating procedures for the Pajarito Site Critical Assembly Facility

    International Nuclear Information System (INIS)

    Malenfant, R.E.

    1983-03-01

    Operating procedures consistent with DOE Order 5480.2, Chapter VI, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Pajarito Site Critical Assembly Facility of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1973 and apply to any criticality experiment performed at the facility

  3. Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — For more than 30 years The Combustion Research Facility (CRF) has served as a national and international leader in combustion science and technology. The need for a...

  4. Operation of Temporary Radioactive waste stoprage facility

    Energy Technology Data Exchange (ETDEWEB)

    Kinseem, A A; Abulfaraj, W H; Sohsah, M A; Kamal, S M; Mamoon, A M [Nuclear Engineering Department, Faculty of Engineering, King Abdelazizi University jeddah-21413, Saudi Arabia (Saudi Arabia)

    1997-12-31

    Radionuclides of various half lives have been in use for several years years at different Departments of king Abdulaziz university, the university hospital, and research center. The use of unsealed radionuclides in many laboratories, resulted in considerable amounts of solid and liquid radwaste, mainly radiopharmaceuticals. To avoid accumulation of radwastes in working areas, a temporary radioactive waste storage facility was built. Segregation of radwastes according to type was carried out, followed by collection into appropriate containers and transfer to the storage facility. Average radiation dose rate inside the store was maintained at about 75 {mu} h{sup -1} through use of appropriate shielding. The dose rates at points one meter outside the store walls were maintained at about 15-20 {mu}Sv h{sup -1}. Utilization of radioisotopes during the period of 1991-1995 resulted in a volume of about 1.8 m{sup 3} of solid radwaste and about 200 L of liquid radwaste. Records of the store inventory are maintained in a computer database, listing dates, types, activities and packaging data pertinent to the radwastes delivered to the store. Quality assurance procedures are implemented during the different stages of the radwaste collection, transportation, and storage. Construction and operation of the storage facility comply with radiation safety requirements for the workers handling the radwastes, the public and the environment. The capacity of the storage facility is such that it will accommodate storage of generated radwastes of long half life up to year 2016. Permanent disposal of such radwastes may be indicated afterwards. 2 figs., 3 tabs.

  5. Defense Waste Processing Facility radioactive operations -- Part 2, Glass making

    International Nuclear Information System (INIS)

    Carter, J.T.; Rueter, K.J.; Ray, J.W.; Hodoh, O.

    1996-01-01

    The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation's first and world's largest vitrification facility. Following a ten year construction period and nearly 3 year non-radioactive test program, the DWPF began radioactive operations in March, 1996. The results of the first 8 months of radioactive operations are presented. Topics include facility production from waste preparation batching to canister filling

  6. Concrete Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This is a 20,000-sq ft laboratory that supports research on all aspects of concrete and materials technology. The staff of this facility offer wide-ranging expertise...

  7. Two years of operating experience with the Seattle clinical neutron therapy facility

    International Nuclear Information System (INIS)

    Risler, R.; Brossard, S.; Eenmaa, J.; Kalet, I.; Wootton, P.

    1987-01-01

    After five years of planning, equipment acquisition, facility construction and beam testing the Seattle Clinical Neutron Therapy facility became operational in October 1984. In the past two years nearly 300 people have been treated in clinical trials. During this time 82 % of the planned treatment sessions were performed on schedule, 3 % had to be rescheduled for patient related reasons and 15 % because of equipment problems. The facility is at present running on a 5 days/week schedule: Three ten-hour treatment days, one maintenance day and one research day (radiobiology, therapy related physics). Short runs for short lived isotopes are done between patient treatments. The isocentric gantry, capable of 360 rotation is equipped with a variable collimator with 40 independent leaves. This collimation system allows the use of complex field shapes without the necessity of handling radioactive components like collimator inserts or blocks. It has turned out to be a very essential part for the efficient operation of the facility. Major causes for equipment downtime were associated with the control system, the beryllium target system, RF and magnet systems and the treatment gantry. (author)

  8. Shock Thermodynamic Applied Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Shock Thermodynamic Applied Research Facility (STAR) facility, within Sandia’s Solid Dynamic Physics Department, is one of a few institutions in the world with a...

  9. High temperature aircraft research furnace facilities

    Science.gov (United States)

    Smith, James E., Jr.; Cashon, John L.

    1992-01-01

    Focus is on the design, fabrication, and development of the High Temperature Aircraft Research Furnace Facilities (HTARFF). The HTARFF was developed to process electrically conductive materials with high melting points in a low gravity environment. The basic principle of operation is to accurately translate a high temperature arc-plasma gas front as it orbits around a cylindrical sample, thereby making it possible to precisely traverse the entire surface of a sample. The furnace utilizes the gas-tungsten-arc-welding (GTAW) process, also commonly referred to as Tungsten-Inert-Gas (TIG). The HTARFF was developed to further research efforts in the areas of directional solidification, float-zone processing, welding in a low-gravity environment, and segregation effects in metals. The furnace is intended for use aboard the NASA-JSC Reduced Gravity Program KC-135A Aircraft.

  10. Field Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Field Research Facility (FRF) located in Duck, N.C. was established in 1977 to support the U.S. Army Corps of Engineers' coastal engineering mission. The FRF is...

  11. Nuclear Security Management for Research Reactors and Related Facilities

    International Nuclear Information System (INIS)

    2016-03-01

    This publication provides a single source guidance to assist those responsible for the implementation of nuclear security measures at research reactors and associated facilities in developing and maintaining an effective and comprehensive programme covering all aspects of nuclear security on the site. It is based on national experience and practices as well as on publications in the field of nuclear management and security. The scope includes security operations, security processes, and security forces and their relationship with the State’s nuclear security regime. The guidance is provided for consideration by States, competent authorities and operators

  12. Fuel supply shutdown facility interim operational safety requirements

    International Nuclear Information System (INIS)

    Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

    1995-01-01

    These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

  13. Effect of facility on the operative costs of distal radius fractures.

    Science.gov (United States)

    Mather, Richard C; Wysocki, Robert W; Mack Aldridge, J; Pietrobon, Ricardo; Nunley, James A

    2011-07-01

    The purpose of this study was to investigate whether ambulatory surgery centers can deliver lower-cost care and to identify sources of those cost savings. We performed a cost identification analysis of outpatient volar plating for closed distal radius fractures at a single academic medical center. Multiple costs and time measures were taken from an internal database of 130 consecutive patients and were compared by venue of treatment, either an inpatient facility or an ambulatory, stand-alone surgery facility. The relationships between total cost and operative time and multiple variables, including fracture severity, patient age, gender, comorbidities, use of bone graft, concurrent carpal tunnel release, and surgeon experience, were examined, using multivariate analysis and regression modeling to identify other cost drivers or explanatory variables. The mean operative cost was considerably greater at the inpatient facility ($7,640) than at the outpatient facility ($5,220). Cost drivers of this difference were anesthesia services, post-anesthesia care unit, and operating room costs. Total surgical time, nursing time, set-up, and operative times were 33%, 109%, 105%, and 35% longer, respectively, at the inpatient facility. There was no significant difference between facilities for the additional variables, and none of those variables independently affected cost or operative time. The only predictor of cost and time was facility type. This study supports the use of ambulatory stand-alone surgical facilities to achieve efficient resource utilization in the operative treatment of distal radius fractures. We also identified several specific costs and time measurements that differed between facilities, which can serve as potential targets for tertiary facilities to improve utilization. Economic and Decisional Analysis III. Copyright © 2011 American Society for Surgery of the Hand. Published by Elsevier Inc. All rights reserved.

  14. Operational Experience of an Open-Access, Subscription-Based Mass Spectrometry and Proteomics Facility

    Science.gov (United States)

    Williamson, Nicholas A.

    2018-03-01

    This paper discusses the successful adoption of a subscription-based, open-access model of service delivery for a mass spectrometry and proteomics facility. In 2009, the Mass Spectrometry and Proteomics Facility at the University of Melbourne (Australia) moved away from the standard fee for service model of service provision. Instead, the facility adopted a subscription- or membership-based, open-access model of service delivery. For a low fixed yearly cost, users could directly operate the instrumentation but, more importantly, there were no limits on usage other than the necessity to share available instrument time with all other users. All necessary training from platform staff and many of the base reagents were also provided as part of the membership cost. These changes proved to be very successful in terms of financial outcomes for the facility, instrument access and usage, and overall research output. This article describes the systems put in place as well as the overall successes and challenges associated with the operation of a mass spectrometry/proteomics core in this manner. [Figure not available: see fulltext.

  15. SUPERCONDUCTING RADIO-FREQUENCY MODULES TEST FACILITY OPERATING EXPERIENCE

    International Nuclear Information System (INIS)

    Soyars, W.; Bossert, R.; Darve, C.; Degraff, B.; Klebaner, A.; Martinez, A.; Pei, L.; Theilacker, J.

    2008-01-01

    Fermilab is heavily engaged and making strong technical contributions to the superconducting radio-frequency research and development program (SRF R and D). Four major SRF test areas are being constructed to enable vertical and horizontal cavity testing, as well as cryomodule testing. The existing Fermilab cryogenic infrastructure has been modified to service the SRF R and D needs. The project's first stage has been successfully completed, which allows for distribution of cryogens for a single-cavity cryomodule using the existing Cryogenic Test Facility (CTF) that houses three Tevatron satellite refrigerators. The cooling capacity available for cryomodule testing at Meson Detector Building (MDB) results from the liquefaction capacity of the CTF cryogenic system. The cryogenic system for a single 9-cell cryomodule is currently operational. The paper describes the status, challenges and operational experience of the initial phase of the project

  16. Development of operation control expert system for off-site facilities

    Energy Technology Data Exchange (ETDEWEB)

    Takeuchi, Masaaki

    1988-09-01

    Concerning off-site facilities of oil refinary, changes of facilities and equipment are frequently made in order to cope flexibly with the market trends and changes of the social environment. In addition, it is desirable to introduce computerization into control and manipulation of off-site facilities for its fast, safe and sure operation. In order to achieve the above, against the existing exclusively control-oriented system, it is necessary to add the processing and generating functions to combinations between valves to be shut and piping as well as equipment to be used along the whole extent of the oil flow in the system and to add the function which makes verification of the above functions easy through a dialogue between users and the system. In order to realize the above, Cosmo Oil and Yokokawa Denki developed jointly an operation control expert system for off-site facilities and the system started its actual operation from October 1986. This article is an outline of the system. The result of its actual operation for one and a half years since its inception showed that the system was operated only by the staff responsible for the operation of the facilities, the workload was reduced to 1/3-1/4 of the workload before the adoption of the system and absolutely no omission of work nor mistake was experienced. (2 figs)

  17. Design of Safety Parameter Monitoring Function in a Research Reactor Facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

  18. Design of Safety Parameter Monitoring Function in a Research Reactor Facility

    International Nuclear Information System (INIS)

    Park, Jaekwan; Suh, Yongsuk

    2014-01-01

    The primary purpose of the safety parameter monitoring system (SPDS) is to help operating personnel in the control room make quick assessments of the plant safety status. Thus, the basic function of the SPDS is a provision of a continuous indication of plant parameters or derived variables representative of the safety status of the plant. NUREG-0737 Supplement 1 provides details of the functional criteria for the SPDS, as one of the action plan requirements from TMI accident. The system provides various functions as follows: · Alerting based on safety function decision logics, · Success path analysis to achieve the integrity of the safety functions, · 3 layer display architecture - safety function, success path display for each safety function, system summary and equipment details for each safety function, · Integration with computer-based procedure. According to a Notice of the NSSC No. 2012-31, a research reactor facility generating more than 2 MW of power should also be furnished with the SPDS for emergency preparedness. Generally, a research reactor is a small size facility, and its number of instrumentations is fewer than that of NPPs. In particular, it is actually hard to have various and powerful functions from an economic perspective. Therefore, a safety parameter display system optimized for a research reactor facility must be proposed. This paper provides the requirement analysis results and proposes the design of safety parameter monitoring function for a research reactor. The safety parameter monitoring function supporting control room personnel during emergency conditions should be designed in a research reactor facility. The facility size and number of signals are smaller than that of the power plants. Also, it is actually hard to have various and powerful functions of nuclear power plants from an economic perspective. Thus, a safety parameter display system optimized to a research reactor must be proposed. First, we found important design items

  19. Management and Development of the RT Research Facilities and Infrastructures

    International Nuclear Information System (INIS)

    Kim, Won Ho; Nho, Young Chang; Kim, Jae Sung

    2009-01-01

    The purpose of this project are to operate the core facilities of the research for the Radiation Technology in stable and to assist the research activities efficiently in the industry, academic, and research laboratory. By developing the infrastructure of the national radio technology industry, we can activate the researching area of the RT and the related industry, and obtain the primary and original technology. The key point in the study of the RT and the assistance of the industry, academic, and research laboratory for the RT area smoothly, is managing the various of unique radiation facilities in our country. The gamma Phytotron and Gene Bank are essential in the agribiology because these facilities are used to preserve and utilize the genes and to provide an experimental field for the environment and biotechnology. The Radiation Fusion Technology research supporting facilities are the core support facilities, and are used to develop the high-tech fusion areas. In addition, the most advanced analytical instruments, whose costs are very high, should be managed in stable and be utilized in supporting works, and the experimental animal supporting laboratory and Gamma Cell have to be maintained in high level and managed in stable also. The ARTI have been developed the 30MeV cyclotron during 2005∼2006, aimed to produce radioisotopes and to research the beam applications as a result of the project, 'Establishment of the Infrastructure for the Atomic Energy Research Expansion', collaborated with the Korea Institute of Radiological and Medical Sciences. In addition, the ARTI is in the progress of establishing cyclotron integrated complex as a core research facility, using a proton beam to produce radioisotopes and to support a various research areas. The measurement and evaluation of the irradiation dose, and irradiation supporting technology of the Good Irradiation Practice(GIP) are essential in various researching areas. One thing to remember is that the publicity

  20. Geophysical Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Geophysical Research Facility (GRF) is a 60 ft long × 22 ft wide × 7 ft deep concrete basin at CRREL for fresh or saltwater investigations and can be temperature...

  1. Access to major overseas research facilities

    International Nuclear Information System (INIS)

    Bolderman, J. W.

    1997-01-01

    This paper will describe four schemes which have been established to permit Australian researchers access to some of the most advanced overseas research facilities. These include, access to Major Research Facilities Program, the Australian National Beamline Facility at the Photon Factory, the Australian Synchrotron Research Program and the ISIS Agreement. The details of each of these programs is discussed and the statistics on the scientific output provided. All programs are managed on behalf of the Department of Industry, Science and Tourism by the Australian Nuclear Science and Technology Organisation. One hundred and thirteen senior scientists plus forty, one postgraduate, students were supported through these schemes during the 1996-1997 financial year

  2. Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-07-02

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  3. Developing operating procedures for a low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  4. Developing operating procedures for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G.

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures

  5. Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Liu, James C.; Rokni, Sayed H.; /SLAC; Vylet, Vaclav; /Jefferson Lab

    2009-12-11

    The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power ({approx} 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

  6. Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

    International Nuclear Information System (INIS)

    Liu, James C.; Rokni, Sayed H.; Vylet, Vaclav

    2009-01-01

    The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power (∼ 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

  7. Unique life sciences research facilities at NASA Ames Research Center

    Science.gov (United States)

    Mulenburg, G. M.; Vasques, M.; Caldwell, W. F.; Tucker, J.

    1994-01-01

    The Life Science Division at NASA's Ames Research Center has a suite of specialized facilities that enable scientists to study the effects of gravity on living systems. This paper describes some of these facilities and their use in research. Seven centrifuges, each with its own unique abilities, allow testing of a variety of parameters on test subjects ranging from single cells through hardware to humans. The Vestibular Research Facility allows the study of both centrifugation and linear acceleration on animals and humans. The Biocomputation Center uses computers for 3D reconstruction of physiological systems, and interactive research tools for virtual reality modeling. Psycophysiological, cardiovascular, exercise physiology, and biomechanical studies are conducted in the 12 bed Human Research Facility and samples are analyzed in the certified Central Clinical Laboratory and other laboratories at Ames. Human bedrest, water immersion and lower body negative pressure equipment are also available to study physiological changes associated with weightlessness. These and other weightlessness models are used in specialized laboratories for the study of basic physiological mechanisms, metabolism and cell biology. Visual-motor performance, perception, and adaptation are studied using ground-based models as well as short term weightlessness experiments (parabolic flights). The unique combination of Life Science research facilities, laboratories, and equipment at Ames Research Center are described in detail in relation to their research contributions.

  8. Facility Will Help Transition Models Into Operations

    Science.gov (United States)

    Kumar, Mohi

    2009-02-01

    The U.S. National Oceanic and Atmospheric Administration's Space Weather Prediction Center (NOAA SWPC), in partnership with the U.S. Air Force Weather Agency (AFWA), is establishing a center to promote and facilitate the transition of space weather models to operations. The new facility, called the Developmental Testbed Center (DTC), will take models used by researchers and rigorously test them to see if they can withstand continued use as viable warning systems. If a model used in a space weather warning system crashes or fails to perform well, severe consequences can result. These include increased radiation risks to astronauts and people traveling on high-altitude flights, national security vulnerabilities from the loss of military satellite communications, and the cost of replacing damaged military and commercial spacecraft.

  9. Annual report of Department of Research Reactor and Tandem Accelerator, JFY2014. Operation, Utilization and Technical Development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

    International Nuclear Information System (INIS)

    Osa, Akihiko; Imahashi, Masaki; Hirane, Nobuhiko; Motome, Yuiko; Tayama, Hidekazu; Tamura, Itaru; Harada, Yuko; Sakata, Mami; Kadokura, Masakazu; Takita, Chiharu

    2017-02-01

    The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3 (Japan Research Reactor No.3), JRR-4 (Japan Research Reactor No.4), NSRR (Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes the activities of our department in fiscal year of 2014. We carried out the operation and maintenance, utilization, upgrading of utilization techniques, safety administration, and international cooperation. Also contained are lists of publications, meetings, granted permissions on laws and regulations concerning atomic energy, outcomes in service and technical developments and so on. (author)

  10. Annual report of Department of Research Reactor and Tandem Accelerator, JFY2013. Operation, Utilization and Technical Development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

    International Nuclear Information System (INIS)

    Kashima, Yoichi; Murayama, Yoji; Nakamura, Kiyoshi; Uno, Yuki; Hirane, Nobuhiko; Ohuchi, Hitoshi; Ishizaki, Nobuhiro; Matsumura, Taichi; Nagahori, Kazuhisa; Harada, Yuko; Kadokura, Masakazu; Machi, Sumire; Takita, Chiharu

    2015-02-01

    The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3(Japan Research Reactor No.3), JRR-4(Japan Research Reactor No.4), NSRR(Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes the activities of our department in fiscal year of 2013. We carried out the operation and maintenance, utilization, upgrading of utilization techniques, safety administration and international cooperation. Also contained are lists of publications, meetings, granted permissions on laws and regulations concerning atomic energy, outcomes in service and technical developments and so on. (author)

  11. Facility Operations 1993 fiscal year work plan: WBS 1.3.1

    Energy Technology Data Exchange (ETDEWEB)

    1992-11-01

    The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO{sub 3}) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP).

  12. Facility Operations 1993 fiscal year work plan: WBS 1.3.1

    International Nuclear Information System (INIS)

    1992-11-01

    The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO 3 ) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP)

  13. Meson facility. Powerful new research tool

    International Nuclear Information System (INIS)

    Lobashev, V.M.; Tavkhelidze, A.N.

    A meson facility is being built at the Institute of Nuclear Research, USSR Academy of Sciences, in Troitsk, where the Scientific Center, USSR Academy of Sciences is located. The facility will include a linear accelerator for protons and negative hydrogen ions with 600 MeV energy and 0.5-1 mA beam current. Some fundamental studies that can be studied at a meson facility are described in the areas of elementary particles, neutron physics, solid state physics, and applied research. The characteristics of the linear accelerator are given and the meson facility's experimental complex is described

  14. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  15. Safety Research Experiment Facilities, Idaho National Engineering Laboratory, Idaho. Draft environmental statement

    International Nuclear Information System (INIS)

    1977-01-01

    This environmental statement was prepared in accordance with the National Environmental Policy Act of 1969 (NEPA) in support of the Energy Research and Development Administration's (ERDA) proposal for legislative authorization and appropriations for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evalution of some design options and in the assessment of the long-term potential risk associated with wide-scale deployment of the FBR

  16. Access to major overseas research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bolderman, J. W. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia)

    1997-12-31

    This paper will describe four schemes which have been established to permit Australian researchers access to some of the most advanced overseas research facilities. These include, access to Major Research Facilities Program, the Australian National Beamline Facility at the Photon Factory, the Australian Synchrotron Research Program and the ISIS Agreement. The details of each of these programs is discussed and the statistics on the scientific output provided. All programs are managed on behalf of the Department of Industry, Science and Tourism by the Australian Nuclear Science and Technology Organisation. One hundred and thirteen senior scientists plus forty, one postgraduate, students were supported through these schemes during the 1996-1997 financial year. 1 fig.

  17. Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2017-06-15

    To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper.

  18. Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

    International Nuclear Information System (INIS)

    Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak

    2017-01-01

    To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper

  19. High Performance Computing Facility Operational Assessment, FY 2011 Oak Ridge Leadership Computing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Baker, Ann E [ORNL; Bland, Arthur S Buddy [ORNL; Hack, James J [ORNL; Barker, Ashley D [ORNL; Boudwin, Kathlyn J. [ORNL; Kendall, Ricky A [ORNL; Messer, Bronson [ORNL; Rogers, James H [ORNL; Shipman, Galen M [ORNL; Wells, Jack C [ORNL; White, Julia C [ORNL

    2011-08-01

    Oak Ridge National Laboratory's Leadership Computing Facility (OLCF) continues to deliver the most powerful resources in the U.S. for open science. At 2.33 petaflops peak performance, the Cray XT Jaguar delivered more than 1.5 billion core hours in calendar year (CY) 2010 to researchers around the world for computational simulations relevant to national and energy security; advancing the frontiers of knowledge in physical sciences and areas of biological, medical, environmental, and computer sciences; and providing world-class research facilities for the nation's science enterprise. Scientific achievements by OLCF users range from collaboration with university experimentalists to produce a working supercapacitor that uses atom-thick sheets of carbon materials to finely determining the resolution requirements for simulations of coal gasifiers and their components, thus laying the foundation for development of commercial-scale gasifiers. OLCF users are pushing the boundaries with software applications sustaining more than one petaflop of performance in the quest to illuminate the fundamental nature of electronic devices. Other teams of researchers are working to resolve predictive capabilities of climate models, to refine and validate genome sequencing, and to explore the most fundamental materials in nature - quarks and gluons - and their unique properties. Details of these scientific endeavors - not possible without access to leadership-class computing resources - are detailed in Section 4 of this report and in the INCITE in Review. Effective operations of the OLCF play a key role in the scientific missions and accomplishments of its users. This Operational Assessment Report (OAR) will delineate the policies, procedures, and innovations implemented by the OLCF to continue delivering a petaflop-scale resource for cutting-edge research. The 2010 operational assessment of the OLCF yielded recommendations that have been addressed (Reference Section 1) and

  20. 78 FR 29393 - University of Missouri-Columbia Facility Operating License No. R-103

    Science.gov (United States)

    2013-05-20

    ... Facility Operating License No. R-103 AGENCY: Nuclear Regulatory Commission. ACTION: License renewal... the renewal of Facility Operating License No. R-103 (``Application''), which currently authorizes the... application for the renewal of Facility Operating License No. R-103, which, currently authorizes the licensee...

  1. First operations of the LNS heavy ions facility

    International Nuclear Information System (INIS)

    Calabretta, L.; Ciavola, G.; Cuttone, G.; Gammino, S.; Gmaj, P.; Migneco, E.; Raia, G.; Rifuggiato, D.; Rovelli, A.; Sura, J.; Scuderi, V.; Acerbi, E.; Alessandria, F.; Bellomo, G.; Bosotti, A.; Martinis, C. de; Giove, D.; Michelato, P.; Pagani, C.; Rossi, L.

    1996-01-01

    A heavy ion facility is now available at laboratorio nazionale del Sud (LNS) of Catania. It can deliver beams with an energy up to 100 MeV/amu. The facility is based on a 15 MV HVEC tandem and a K=800 superconducting cyclotron as booster. During the last year, the facility came into operation. A 58 Ni beam delivered by the tandem has been radially injected in the SC and then has been accelerated and extracted at 30 MeV/amu. In this paper the status of the facility together with the experience gained during the commissioning will be extensively reported. (orig.)

  2. Cost calculations for decommissioning and dismantling of nuclear research facilities

    International Nuclear Information System (INIS)

    Andersson, I.; Backe, S.; Cato, A.; Lindskog, S.; Efraimsson, H.; Iversen, Klaus; Salmenhaara, S.; Sjoeblom, R.

    2008-07-01

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  3. Cost calculations for decommissioning and dismantling of nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

    2008-07-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  4. Embracing Safe Ground Test Facility Operations and Maintenance

    Science.gov (United States)

    Dunn, Steven C.; Green, Donald R.

    2010-01-01

    Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

  5. Operating a production facility without a CO and O agreement

    International Nuclear Information System (INIS)

    Smith, M. R.

    2000-01-01

    Issues that arise when an oil or natural gas facility is operated without a specific construction, ownership and operating (CO and O) agreement was explored. The lack of such an agreement may be due to the parties' inability to reach agreement, reliance on the land operating agreement, or the lack of diligent follow-up on the drafting, revision and execution of operating agreements. The paper examines the nature of ownership interests that obtain in the absence of a CO and O, the common situation in respect to CO and O agreements where the document has been circulated but has not been signed by the owners. A number of actual cases were cited to illustrate the effects of such an omission. It was concluded that ideally, a fully executed CO and O for each facility which deals specifically with the owners involved with the particular facility is the best of all worlds. However given the nature of some facilities, the expense, time and effort required to prepare and execute a separate CO and O, it is frequently omitted; in such situations it is convenient to fall back on the 1990 Operating Procedure of CAPL, which while general in nature and cannot adequately deal with every situation, deals with many common problems associated with the operation of facilities. It is recommended that even if a complete CO and O agreement cannot be executed, interim binding agreements should be used to avoid uncertainty until such time as a complete agreement can be finalized. A clause-by-clause comparison of the 1990 CAPL Operating Procedure and a 1996 model CO and O agreement, prepared by the Petroleum Joint Venture Association (PJVA), is appended

  6. Transonic Experimental Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Transonic Experimental Research Facility evaluates aerodynamics and fluid dynamics of projectiles, smart munitions systems, and sub-munitions dispensing systems;...

  7. Flexible Electronics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Flexible Electronics Research Facility designs, synthesizes, tests, and fabricates materials and devices compatible with flexible substrates for Army information...

  8. 200 Area treated effluent disposal facility operational test report

    International Nuclear Information System (INIS)

    Crane, A.F.

    1995-01-01

    This document reports the results of the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These completed operational testing activities demonstrated the functional, operational and design requirements of the 200 Area TEDF have been met

  9. Operating experience review -- Conduct of operations at Department of Energy facilities

    International Nuclear Information System (INIS)

    1994-08-01

    This research examined human error related occurrences, reported in the ORPS database, for the purpose of identifying weaknesses in the implementation of the guidance regarding the Conduct of Operations contained in DOE 5480.19. Specifically, this research examined three separate samples of occurrence reports from Defense Program facilities, which cited human error as a direct or contributing cause. These reports were evaluated using a coding scheme which incorporated the guidelines present in 5480.19, as well as a number of generic human factors concerns. The second chapter of this report summarizes the coding scheme which was used to evaluate the occurrence reports. Since the coding scheme is quite lengthy, only the parts of the scheme needed to make the remainder of the report clear are included in this chapter. Details on the development and content of the coding scheme are reported in Appendices A, B, and C. Chapter 3 presents the analysis of three different data sets. This chapter demonstrates that similar results were obtained across different data sets, collected at different points in time, and coded by different raters. The implications of the results obtained in Chapter 3 are discussed in Chapter 4. This chapter makes a number of suggestions for reducing the problems found in the occurrence reports. Chapter 5 applies the methodology that has been developed in this report to two facilities at Los Alamos National Laboratory. Finally, Chapter 6 reiterates the major findings of this report. Several additional analyses appear in appendices at the end of this report

  10. Technological Advances, Human Performance, and the Operation of Nuclear Facilities

    Science.gov (United States)

    Corrado, Jonathan K.

    Many unfortunate and unintended adverse industrial incidents occur across the United States each year, and the nuclear industry is no exception. Depending on their severity, these incidents can be problematic for people, the facilities, and surrounding environments. Human error is a contributing factor in many such incidents. This dissertation first explored the hypothesis that technological changes that affect how operators interact within the systems of the nuclear facilities exacerbate the cost of incidents caused by human error. I conducted a review of nuclear incidents in the United States from 1955 through 2010 that reached Level 3 (serious incident) or higher on the International Nuclear Events Scale (INES). The cost of each incident at facilities that had recently undergone technological changes affecting plant operators' jobs was compared to the cost of events at facilities that had not undergone changes. A t-test determined a statistically significant difference between the two groups, confirming the hypothesis. Next, I conducted a follow-on study to determine the impact of the incorporation of new technologies into nuclear facilities. The data indicated that spending more money on upgrades increased the facility's capacity as well as the number of incidents reported, but the incident severity was minor. Finally, I discuss the impact of human error on plant operations and the impact of evolving technology on the 21st-century operator, proposing a methodology to overcome these challenges by applying the systems engineering process.

  11. The Soreq Applied Research Accelerator Facility (SARAF): Overview, research programs and future plans

    Science.gov (United States)

    Mardor, Israel; Aviv, Ofer; Avrigeanu, Marilena; Berkovits, Dan; Dahan, Adi; Dickel, Timo; Eliyahu, Ilan; Gai, Moshe; Gavish-Segev, Inbal; Halfon, Shlomi; Hass, Michael; Hirsh, Tsviki; Kaiser, Boaz; Kijel, Daniel; Kreisel, Arik; Mishnayot, Yonatan; Mukul, Ish; Ohayon, Ben; Paul, Michael; Perry, Amichay; Rahangdale, Hitesh; Rodnizki, Jacob; Ron, Guy; Sasson-Zukran, Revital; Shor, Asher; Silverman, Ido; Tessler, Moshe; Vaintraub, Sergey; Weissman, Leo

    2018-05-01

    The Soreq Applied Research Accelerator Facility (SARAF) is under construction in the Soreq Nuclear Research Center at Yavne, Israel. When completed at the beginning of the next decade, SARAF will be a user facility for basic and applied nuclear physics, based on a 40 MeV, 5 mA CW proton/deuteron superconducting linear accelerator. Phase I of SARAF (SARAF-I, 4 MeV, 2 mA CW protons, 5 MeV 1 mA CW deuterons) is already in operation, generating scientific results in several fields of interest. The main ongoing program at SARAF-I is the production of 30 keV neutrons and measurement of Maxwellian Averaged Cross Sections (MACS), important for the astrophysical s-process. The world leading Maxwellian epithermal neutron yield at SARAF-I (5 × 10^{10} epithermal neutrons/s), generated by a novel Liquid-Lithium Target (LiLiT), enables improved precision of known MACSs, and new measurements of low-abundance and radioactive isotopes. Research plans for SARAF-II span several disciplines: precision studies of beyond-Standard-Model effects by trapping light exotic radioisotopes, such as 6He, 8Li and 18, 19, 23Ne, in unprecedented amounts (including meaningful studies already at SARAF-I); extended nuclear astrophysics research with higher energy neutrons, including generation and studies of exotic neutron-rich isotopes relevant to the rapid (r-) process; nuclear structure of exotic isotopes; high energy neutron cross sections for basic nuclear physics and material science research, including neutron induced radiation damage; neutron based imaging and therapy; and novel radiopharmaceuticals development and production. In this paper we present a technical overview of SARAF-I and II, including a description of the accelerator and its irradiation targets; a survey of existing research programs at SARAF-I; and the research potential at the completed facility (SARAF-II).

  12. Trends of researches for fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Ozawa, Yasutomo; Enoto, Takeaki

    1975-01-01

    The role of a fusion neutron radiation test facility in the development of a scientific feasibility experimental reactor or demonstration fusion power reactor plant would be analogous to the role of the materials testing and experimental reactors in the development of fission power reactor. While the material testing fission reactor has been developed after successful operation of fission reactors, in the case of fusion reactor development it is desirable to realize the fusion engineering research facility (FERF) in-phase to the development of SFX and/or demonstration fusion power reactor plants. Here so called FERF in near future is the Controlled Thermonuclear Reactor which provides the high-intensity and high-energy neutron and plasma source whether the net power output is produced or not. From the point of direct attainment to SFX, we would like to emphasize that FEFE is the royal road leading to the goal of successful achievement of CTR program and could be useful for the experiment on impurity effects caused by neutron and plasma irradiations onto the wall material for SFX. Further, we rather suppose that hybrid FERF-fission assembly could be fairly and easily realizable in near future. (auth.)

  13. Safety research experiment facilities, Idaho National Engineering Laboratory, Idaho. Final environmental impact statement

    International Nuclear Information System (INIS)

    Liverman, J.L.

    1977-09-01

    This environmental statement was prepared for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evaluation of some design options and in the assessment of the long-term potential risk associated with wide-acale deployment of the FBR

  14. DOE research and development and field facilities

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    This report describes the roles of DOE's headquarters, field offices, major multiprogram laboratories, Energy Technology and Mining Operations Centers, and other government-owned, contractor-operated facilities which are located in all regions of the United States. It gives brief descriptions of resources, activities, and capabilities of each field facility (sections III through V). These represent a cumulative capital investment of $12 billion and involve a work force of approximately 12,000 government (field) employees and approximately 100,000 contractor employees.

  15. First operations of the LNS heavy ions facility

    Energy Technology Data Exchange (ETDEWEB)

    Calabretta, L. [INFN-LNS, Catania (Italy); Ciavola, G. [INFN-LNS, Catania (Italy); Cuttone, G. [INFN-LNS, Catania (Italy); Gammino, S. [INFN-LNS, Catania (Italy); Gmaj, P. [INFN-LNS, Catania (Italy); Migneco, E. [INFN-LNS, Catania (Italy); Raia, G. [INFN-LNS, Catania (Italy); Rifuggiato, D. [INFN-LNS, Catania (Italy); Rovelli, A. [INFN-LNS, Catania (Italy); Sura, J. [INFN-LNS, Catania (Italy); Scuderi, V. [INFN-LNS, Catania (Italy); Acerbi, E. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Alessandria, F. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Bellomo, G. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Bosotti, A. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Martinis, C. de [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Giove, D. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Michelato, P. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Pagani, C. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Rossi, L. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy)

    1996-11-11

    A heavy ion facility is now available at laboratorio nazionale del Sud (LNS) of Catania. It can deliver beams with an energy up to 100 MeV/amu. The facility is based on a 15 MV HVEC tandem and a K=800 superconducting cyclotron as booster. During the last year, the facility came into operation. A {sup 58}Ni beam delivered by the tandem has been radially injected in the SC and then has been accelerated and extracted at 30 MeV/amu. In this paper the status of the facility together with the experience gained during the commissioning will be extensively reported. (orig.).

  16. Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

    Directory of Open Access Journals (Sweden)

    M. V. Vedernikova

    2017-01-01

    Full Text Available This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia. The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use

  17. Operation technology of the ventilation system of the radioactive waste treatment facility(II) - Design and operation note

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. M.; Lee, B. C.; Bae, S. M. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    As the radioactive waste treatment work, such as compaction and/or solidification of wastes, are done directly by the workers in the Radioactive Waste Treatment Facility, the reasonable design and operation of the ventilation system is essential. In this report, the design criteria and specification of the ventilation equipment, system operation method are described for the effective design and operation of ventilation system in the radioactive waste treatment facility. And the anti-vibration work which was done in the Radioactive Waste Treatment Facility in KAERI to reduce the effect of vibration due to the continuous operation of big rotational equipment, the intake fans and the exhaust fans, are described in the report. 11 refs., 10 figs., 12 tabs. (Author)

  18. Design and operation of the Surry Radwaste Facility

    International Nuclear Information System (INIS)

    Morris, L.L.; Halverson, W.C.

    1993-01-01

    In September 1991, Virginia Power started processing radioactive waste with a new Radwaste Facility at the Surry Power Station near Norfolk, Virginia. The Surry Radwaste Facility (SRF) was designed to process and store liquid waste, laundry waste, dry active waste, radioactive filters and spent ion-exchange resin. It also provides on-site decontamination services and a fully equipped hot machine shop. The NRC has recognized that the amount of planning and design, and the attention to detail, that was expended on the SRF Project in order to minimize personnel exposure and ensure efficient operation, is a licensee strength. Through its first year of operation, the facility has proven very successful. Using evaporation and demineralization, over 30 million liters of liquid have been released with no chemical impurities or detectable radioactivity (excluding tritium). Over 623,000 liters of concentrated boric acid waste liquid have been processed with the Bitumen Solidification System yielding 139,880 liters (660 drums) of low level Class A-Stable waste. Additional economic benefits will be realized as the effectiveness of the processing systems continues to improve due to increased operational experience and ergonomics

  19. Stockbridge Antenna Measurement and Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Stockbridge Antenna Measurement Facility is located 23 miles southwest of AFRL¹s Rome Research Site. This unique measurement facility is designed to evaluate the...

  20. Air Quality Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research FacilityFacilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other facilities...

  1. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    2000-02-03

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  2. Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  3. Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    2000-01-01

    This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  4. Research on adoption of graphic processing system into electric power facilities operation management. Denryoku setsubi kanri gyomu ni okeru zukei shori system no tekiyo ni kansuru kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    Jitsubuchi, Yoshiyasu; Uryu, Kenji; Terasaki, Naoaki (Kyushu Electric Power Co., Inc., Fukuoka (Japan))

    1989-03-30

    In the technical department of electric power companies, there are innumerable single line diagram, machinery arrangement plan and other facilities drawings. Based on those drawings, facilities planning, work design, construction plan, maintenance and management data, etc. are made, for which making heightening is desired in efficiency of drawing filing management. Therefore, research was made on the adoption of CAD technology through modeling power transmission line, and power generating and transforming station operation management. First for the application of power transmission facilities, the power transmission line plan and facilities information were planned to be unified in management. Ie., the power transmission line plan and profile being shown on the display, symbols of steel towers, cable lines, etc. were further picked by mouth to easily substantiate the facilities. While image input and CAD of drawing were made in combined treatment. Then for the application to the power generating and transforming facilities, the single line diagram and facilities information were unified in management, together with demonstration of data interchangeability among different kinds of CAD system. 13 figs., 9 tabs.

  5. Interim Storage Facility for LLW of Decommissioning Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Amato, S.; Ugolini, D.; Basile, F. [European Commission, Joint Research Centre, Nuclear Decommissioning and Facility Management Unit, TP 800, Via E. Fermi 2749, 21027 Ispra - VA (Italy)

    2009-06-15

    JRC-Ispra has initiated a Decommissioning and Waste Management (D and WM) Programme of all its nuclear facilities. In the frame of this programme, it has been decided to build an interim storage facility to host conditioned low level waste (LLW) that had been produced during the operation of JRC-Ispra nuclear research reactors and laboratories and that will be produced from their decommissioning. This paper presents the main characteristics of the facility. The storage ISFISF has a rectangular shape with uniform height and it is about 128 m long, 41 m wide and 9 m high. The entire surface affected by the facility, including screening area and access roads, is about 27.000 m{sup 2}. It is divided in three sectors, a central one, about 16 m long, for loading/unloading operations and operational services and two lateral sectors, each about 55 m long, for the conditioned LLW storage. Each storage sector is divided by a concrete wall in two transversal compartments. The ISFISF, whose operational lifetime is 50 years, is designed to host the conditioned LLW boxed in UNI CP-5.2 packages, 2,5 m long, 1.65 m wide, and 1,25 m high. The expected nominal inventory of waste is about 2100 packages, while the maximum storage is 2540 packages, thus a considerably large reserve capacity is available. The packages will be piled in stacks of maximum number of five. The LLW is going to be conditioned with a cement matrix. The maximum weight allowed for each package has been fixed at 16.000 kg. The total radioactivity inventory of waste to be hosted in the facility is about 30 TBq (mainly {beta}/{gamma} emitters). In order to satisfy the structural, seismic, and, most of all, radiological requirements, the external walls of the ISFISF are made of pre-fabricated panels, 32 cm thick, consisting of, from inside to outside, 20 cm of reinforced concrete, 7 cm of insulating material, and again 5 cm of reinforced concrete. For the same reason the roof is made with pre-fabricated panels in

  6. Construction and operation of an improved radiation calibration facility at Brookhaven National Laboratory. Environmental assessment

    International Nuclear Information System (INIS)

    1994-10-01

    Calibration of instruments used to detect and measure ionizing radiation has been conducted over the last 20 years at Brookhaven National Laboratory's (BNL) Radiation Calibration Facility, Building 348. Growth of research facilities, projects in progress, and more stringent Department of Energy (DOE) orders which involve exposure to nuclear radiation have placed substantial burdens on the existing radiation calibration facility. The facility currently does not meet the requirements of DOE Order 5480.4 or American National Standards Institute (ANSI) N323-1978, which establish calibration methods for portable radiation protection instruments used in the detection and measurement of levels of ionizing radiation fields or levels of radioactive surface contaminations. Failure to comply with this standard could mean instrumentation is not being calibrated to necessary levels of sensitivity. The Laboratory has also recently obtained a new neutron source and gamma beam irradiator which can not be made operational at existing facilities because of geometry and shielding inadequacies. These sources are needed to perform routine periodic calibrations of radiation detecting instruments used by scientific and technical personnel and to meet BNL's substantial increase in demand for radiation monitoring capabilities. To place these new sources into operation, it is proposed to construct an addition to the existing radiation calibration facility that would house all calibration sources and bring BNL calibration activities into compliance with DOE and ANSI standards. The purpose of this assessment is to identify potential significant environmental impacts associated with the construction and operation of an improved radiation calibration facility at BNL

  7. Neutron research and facility development at the Oak Ridge Electron Linear Accelerator 1970 to 1995

    International Nuclear Information System (INIS)

    Peelle, R.W.; Harvey, J.A.; Maienschein, F.C.; Weston, L.W.; Olsen, D.K.; Larson, D.C.; Macklin, R.L.

    1982-07-01

    This report reviews the accomplishments of the first decade of operation of the Oak Ridge Electron Linear Accelerator (ORELA) and discusses the plans for the facility in the coming decade. Motivations for scientific and applied research during the next decade are included. In addition, ORELA is compared with competing facilities, and prospects for ORELA's improvement and even replacement are reported. Development efforts for the next few years are outlined that are consistent with the anticipated research goals. Recommendations for hardware development include improving the electron injection system to give much larger short-pulse currents on a reliable basis, constructing an Electron Beam Injector Laboratory to help make this improvement possible, continuing a study of possibly replacing the electron accelerator with a proton machine, and replacing or upgrading the facility's data-acquistion and immediate-analysis computer systems. Increased operating time and more involvement of nuclear theorists are recommended, and an effective staff size for optimum use of this unique facility is discussed. A bibliography of all ORELA-related publications is included

  8. Licensing and Operations of the Clive, Utah Low-Level Containerized Radioactive Waste Disposal Facility- A Continuation of Excellence

    International Nuclear Information System (INIS)

    Ledoux, M. R.; Cade, M. S.

    2002-01-01

    Envirocare's Containerized Waste Facility (CWF) is the first commercial low-level radioactive waste disposal facility to be licensed in the 21st century and the first new site to be opened and operated since the late 1970's. The licensing of this facility has been the culmination of over a decade's effort by Envirocare of Utah at their Clive, Utah site. With the authorization to receive and dispose of higher activity containerized Class A low-level radioactive waste (LLRW), this facility has provided critical access to disposal for the nuclear power industry, as well as the related research and medical communities. This paper chronicles the licensing history and operational efforts designed to address the disposal of containerized LLRW in accordance with state and federal regulations

  9. Frost Effects Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Full-scale study in controlled conditionsThe Frost Effects Research Facility (FERF) is the largest refrigerated warehouse in the United States that can be used for a...

  10. Simulation of facility operations and materials accounting for a combined reprocessing/MOX fuel fabrication facility

    International Nuclear Information System (INIS)

    Coulter, C.A.; Whiteson, R.; Zardecki, A.

    1991-01-01

    We are developing a computer model of facility operations and nuclear materials accounting for a facility that reprocesses spent fuel and fabricates mixed oxide (MOX) fuel rods and assemblies from the recovered uranium and plutonium. The model will be used to determine the effectiveness of various materials measurement strategies for the facility and, ultimately, of other facility safeguards functions as well. This portion of the facility consists of a spent fuel storage pond, fuel shear, dissolver, clarifier, three solvent-extraction stages with uranium-plutonium separation after the first stage, and product concentrators. In this facility area mixed oxide is formed into pellets, the pellets are loaded into fuel rods, and the fuel rods are fabricated into fuel assemblies. These two facility sections are connected by a MOX conversion line in which the uranium and plutonium solutions from reprocessing are converted to mixed oxide. The model of the intermediate MOX conversion line used in the model is based on a design provided by Mike Ehinger of Oak Ridge National Laboratory (private communication). An initial version of the simulation model has been developed for the entire MOX conversion and fuel fabrication sections of the reprocessing/MOX fuel fabrication facility, and this model has been used to obtain inventory difference variance estimates for those sections of the facility. A significant fraction of the data files for the fuel reprocessing section have been developed, but these data files are not yet complete enough to permit simulation of reprocessing operations in the facility. Accordingly, the discussion in the following sections is restricted to the MOX conversion and fuel fabrication lines. 3 tabs

  11. Development of an Extreme Environment Materials Research Facility at Princeton

    International Nuclear Information System (INIS)

    Cohen, A.B.; Gentile, C.A.; Tully, C.G.; Austin, R.; Calaprice, F.; McDonald, K.; Ascione, G.; Baker, G.; Davidson, R.; Dudek, L.; Grisham, L.; Kugel, H.; Pagdon, K.; Stevenson, T.; Woolley, R.; Zwicker, A.

    2010-01-01

    The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a facility for testing various materials under extreme heat and neutron exposure conditions at Princeton. The Extreme Environment Materials Research Facility comprises an environmentally controlled chamber (48 m 3 ) capable of high vacuum conditions, with extreme flux beams and probe beams accessing a central, large volume target. The facility will have the capability to expose large surface areas (1 m 2 ) to 14 MeV neutrons at a fluence in excess of 10 13 n/s. Depending on the operating mode. Additionally beam line power on the order of 15-75 MW/m 2 for durations of 1-15 seconds are planned. The multi-second duration of exposure can be repeated every 2-10 minutes for periods of 10-12 hours. The facility will be housed in the test cell that held the Tokamak Fusion Test Reactor (TFTR), which has the desired radiation and safety controls as well as the necessary loading and assembly infrastructure. The facility will allow testing of various materials to their physical limit of thermal endurance and allow for exploring the interplay between radiation-induced embrittlement, swelling and deformation of materials, and the fatigue and fracturing that occur in response to thermal shocks. The combination of high neutron energies and intense fluences will enable accelerated time scale studies. The results will make contributions for refining predictive failure modes (modeling) in extreme environments, as well as providing a technical platform for the development of new alloys, new

  12. The operation of post-irradiation examination facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eun Ka; Park, Kwang Jun; Lee, Won Sang [and others; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-01-01

    The operation and management of PIE facility was executed in 1993. An indigenous 16 x 16 PWR type fuel assembly (ID No. J44) which was discharged from Kori unit 2 power reactor was transported to KAERI`s PIE facility and in-pool nondestructive examination and hot cell examination for the fuel were carried out. Because the above-mentioned 16 x 16 fuel is different from 14 x 14 fuel in its size and array of fuel rods, several examination and handling equipment for the 16 x 16 type fuel were designed and fabricated. PIE facility was operated in normal condition with the periodical check and inspection of the devices. The filter housing on the roof hood in chemical analysis hot cell was modified mounting air pressure gauge to indicate the optimal filter exchanging time. The burst air heating coil plate and the broken blowing fan of the HVAC system were repaired. The defaced grand packing in pool water circulation pump was replaced with the mechanical seal to prevent the leakage from the pump shaft sealing. The radiation monitoring in the facility was carried out to maintain the safe working condition and several radiation monitors were repaired. Spare parts for the radiation monitoring system were prepared to maintain the facility safely. The performance test of the emergency electric power supply system including UPS, battery and diesel generator was carried out. Oxide layer thickness measuring device for the performance test. Several devices including spent fuel handling equipment for the 17 x 17 PWR type fuel assembly were designed and fabricated for the subsequent PIE of nuclear fuels. 35 tabs., 17 figs., 7 refs. (Author) .new.

  13. Recent operational experiments at the LANSCE facility

    Energy Technology Data Exchange (ETDEWEB)

    Rybarcyk, Lawrence J [Los Alamos National Laboratory

    2010-09-15

    The Los Alamos Neutron Science Center (LANSCE) consists of a pulsed 800-MeV room-temperature linear accelerator and an 800-MeV accumulator ring. It simultaneously provides H{sup +} and H{sup -} beams to several user facilities that have their own distinctive requirements, e.g. intensity, chopping pattern, duty factor, etc.. This multibeam operation presents challenges both from the standpoint of meeting the individual requirements but also achieving good overall performance for the integrated operation. Various aspects of more recent operations including the some of these challenges will be discussed.

  14. Designing a Virtual Research Facility to motivate Professional-Citizen Collaboration

    Science.gov (United States)

    Gay, Pamela

    In order to handle the onslaught of data spilling from telescopes on the Earth and on orbit, CosmoQuest has created a virtual research facility that allows the public to collaborate with science teams on projects that would otherwise lack the necessary human resources. This second-generation citizen science site goes beyond asking people to click on images to also engaging them in taking classes, attending virtual seminars, and participating in virtual star parties. These features were introduced to try and expand the diversity of motivations that bring people to the project and to keep them engaged overtime - just as a research center seeks to bring a diversity of people together to work and learn over time. In creating the CosmoQuest Virtual Research Facility, we sought to answer the question, “What would happen if we provided the public with the same kinds of facilities scientists have, and invite them to be our collaborators?” It had already been observed that the public readily attends public science lectures, open houses at science facilities, and education programs such as star parties. It was hoped that by creating a central facility, we could build a community of people learning and doing science in a productive manner. In order to be successful, we needed to first create the facility, then test if people were coming both to learn and to do science, and finally to verify that people were doing legitimate science. During the past 18 months of operations, we have continued to work through each of these stages, as discussed talk. At this early date, progress is on-going, and much research remains to be done, but all indications show that we are on our way to building a community of people learning and doing science. During 2013-2014, a series of studies looked at the motivations of CosmoQuest users, as well as their forms of site interactions. During this talk, we will review these results, as well as the demographics of our user population.

  15. Installation of the water environment irradiation facility for the IASCC research under the BWR irradiation environment (1)

    International Nuclear Information System (INIS)

    Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Ohmi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu

    2013-10-01

    In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year. (author)

  16. Europlanet Research Infrastructure: Planetary Simulation Facilities

    Science.gov (United States)

    Davies, G. R.; Mason, N. J.; Green, S.; Gómez, F.; Prieto, O.; Helbert, J.; Colangeli, L.; Srama, R.; Grande, M.; Merrison, J.

    2008-09-01

    EuroPlanet The Europlanet Research Infrastructure consortium funded under FP7 aims to provide the EU Planetary Science community greater access for to research infrastructure. A series of networking and outreach initiatives will be complimented by joint research activities and the formation of three Trans National Access distributed service laboratories (TNA's) to provide a unique and comprehensive set of analogue field sites, laboratory simulation facilities, and extraterrestrial sample analysis tools. Here we report on the infrastructure that comprises the second TNA; Planetary Simulation Facilities. 11 laboratory based facilities are able to recreate the conditions found in the atmospheres and on the surfaces of planetary systems with specific emphasis on Martian, Titan and Europa analogues. The strategy has been to offer some overlap in capabilities to ensure access to the highest number of users and to allow for progressive and efficient development strategies. For example initial testing of mobility capability prior to the step wise development within planetary atmospheres that can be made progressively more hostile through the introduction of extreme temperatures, radiation, wind and dust. Europlanet Research Infrastructure Facilties: Mars atmosphere simulation chambers at VUA and OU These relatively large chambers (up to 1 x 0.5 x 0.5 m) simulate Martian atmospheric conditions and the dual cooling options at VUA allows stabilised instrument temperatures while the remainder of the sample chamber can be varied between 220K and 350K. Researchers can therefore assess analytical protocols for instruments operating on Mars; e.g. effect of pCO2, temperature and material (e.g., ± ice) on spectroscopic and laser ablation techniques while monitoring the performance of detection technologies such as CCD at low T & variable p H2O & pCO2. Titan atmosphere and surface simulation chamber at OU The chamber simulates Titan's atmospheric composition under a range of

  17. On exposure management of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1993

    International Nuclear Information System (INIS)

    1994-01-01

    The Law of Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1993 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the the exposure of workers was below the permissible exposure dose in 1993 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of JAERI and PNC. (J.P.N.)

  18. 7 CFR 70.110 - Requirements for sanitation, facilities, and operating procedures in official plants.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Requirements for sanitation, facilities, and operating... Requirements for sanitation, facilities, and operating procedures in official plants. (a) The requirements for sanitation, facilities, and operating procedures in official plants shall be the applicable provisions stated...

  19. Program of experiments for the operating phase of the Underground Research Laboratory

    International Nuclear Information System (INIS)

    Simmons, G.R.; Bilinsky, D.M.; Davison, C.C.; Gray, M.N.; Kjartanson, B.H.; Martin, C.D.; Peters, D.A.; Lang, P.A.

    1992-09-01

    The Underground Research Laboratory (URL) is one of the major research and development facilities that AECL Research has constructed in support of the Canadian Nuclear Fuel Waste Management Program. The URL is a unique geotechnical research facility constructed in previously undisturbed plutonic rock, which was well characterized before construction. The site evaluation and construction phases of the URL project have been completed and the operating phase is beginning. A program of operating phase experiments that address AECL's objectives for in situ testing has been selected. These experiments were subjected to an external peer review and a subsequent review by the URL Experiment Committee in 1989. The comments from the external peer review were incorporated into the experiment plans, and the revised experiments were accepted by the URL Experiment Committee. Summaries of both reviews are presented. The schedule for implementing the experiments and the quality assurance to be applied during implementation are also summarized. (Author) (9 refs., 11 figs.)

  20. Studies and research concerning BNFP: life of project operating expenses for away-from-reactor (AFR) spent fuel storage facility. Final report

    International Nuclear Information System (INIS)

    Shallo, F.A.

    1979-09-01

    Life of Project operating expenses for a licensed Away-From-Reactor (AFR) Spent Fuel Storage Facility are developed in this report. A comprehensive business management structure is established and the functions and responsibilities for the facility organization are described. Contractual provisions for spent fuel storage services are evaluated

  1. MagLev Cobra: Test Facilities and Operational Experiments

    Science.gov (United States)

    Sotelo, G. G.; Dias, D. H. J. N.; de Oliveira, R. A. H.; Ferreira, A. C.; De Andrade, R., Jr.; Stephan, R. M.

    2014-05-01

    The superconducting MagLev technology for transportation systems is becoming mature due to the research and developing effort of recent years. The Brazilian project, named MagLev-Cobra, started in 1998. It has the goal of developing a superconducting levitation vehicle for urban areas. The adopted levitation technology is based on the diamagnetic and the flux pinning properties of YBa2Cu3O7-δ (YBCO) bulk blocks in the interaction with Nd-Fe-B permanent magnets. A laboratory test facility with permanent magnet guideway, linear induction motor and one vehicle module is been built to investigate its operation. The MagLev-Cobra project state of the art is presented in the present paper, describing some construction details of the new test line with 200 m.

  2. Operator-machine interface at a large laser-fusion facility

    International Nuclear Information System (INIS)

    Sutton, J.G.; Howell, J.A.

    1982-01-01

    The operator-machine interface at the Antares Laser Facility provides the operator with a means of controlling the laser system and obtaining operational and performance information. The goal of this interface is to provide an operator with access to the control system in a comfortable way, and to facilitate meeting operational requirements. We describe the philosophy and requirements behind this interface, the hardware used in building it, and the software environment

  3. The space station window observational research facility; a high altitude imaging laboratory

    International Nuclear Information System (INIS)

    Runco, Susan K.; Eppler, Dean B.; Scott, Karen P.

    1999-01-01

    Earth Science will be one of the major research areas to be conducted on the International Space Station. The facilities from which this research will be accomplished are currently being constructed and will be described in this paper. By April 1999, the International Space Station nadir viewing research window fabrication will be completed and ready for installation. The window will provide a 20 inch (51 cm) diameter clear aperture. The three fused silica panes, which make up the window are fabricated such that the total peak-to-valley wavefront error in transmission through the three panes over any six inch diameter aperture does not exceed λ/7 where the reference wavelength is 632.8 nm. The window will have over 90% transmission between about 400 and 750, above 50% transmission between about 310 nm and 1375 nm and 40% transmission between 1386 nm and 2000 nm. The Window Operational Research Facility (WORF) is designed to accommodate payloads using this research window. The WORF will provide access to the International Space Station utilities such as data links, temperature cooling loops and power. Emphasis has been placed on the factors which will make this facility an optimum platform for conducting Earth science research

  4. Facility operations transparency and remote monitoring

    International Nuclear Information System (INIS)

    Beddingfield, David

    2006-01-01

    Remote monitoring technologies offer many opportunities, not only to strengthen IAEA safeguards, but also to improve national, industrial and local oversight of various nuclear operations. Remote monitoring benefits in greater timeliness, reduced inspector presence and improved state-of-health awareness are well-known attributes. However, there is also the capability to organize data into a comprehensive knowledge of the 'normal operating envelope' of a facility. In considering future applications of remote monitoring there is also a need to develop a better understanding of the potential cost-savings versus higher up-front costs and potential long-term maintenance or upgrade costs. (author)

  5. Microcomputer simulation model for facility performance assessment: a case study of nuclear spent fuel handling facility operations

    International Nuclear Information System (INIS)

    Chockie, A.D.; Hostick, C.J.; Otis, P.T.

    1985-10-01

    A microcomputer based simulation model was recently developed at the Pacific Northwest Laboratory (PNL) to assist in the evaluation of design alternatives for a proposed facility to receive, consolidate and store nuclear spent fuel from US commercial power plants. Previous performance assessments were limited to deterministic calculations and Gantt chart representations of the facility operations. To insure that the design of the facility will be adequate to meet the specified throughput requirements, the simulation model was used to analyze such factors as material flow, equipment capability and the interface between the MRS facility and the nuclear waste transportation system. The simulation analysis model was based on commercially available software and application programs designed to represent the MRS waste handling facility operations. The results of the evaluation were used by the design review team at PNL to identify areas where design modifications should be considered. 4 figs

  6. Safety Culture and Best Practices at Japan's Fusion Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Rule, Keith [PPPL

    2014-05-01

    The Safety Monitor Joint Working Group (JWG) is one of the magnetic fusion research collaborations between the US Department of Energy and the government of Japan. Visits by occupational safety personnel are made to participating institutions on a biennial basis. In the 2013 JWG visit of US representatives to Japan, the JWG members noted a number of good safety practices in the safety walkthroughs. These good practices and safety culture topics are discussed in this paper. The JWG hopes that these practices for worker safety can be adopted at other facilities. It is a well-known, but unquantified, safety principle that well run, safe facilities are more productive and efficient than other facilities (Rule, 2009). Worker safety, worker productivity, and high quality in facility operation all complement each other (Mottel, 1995).

  7. The INEL Tritium Research Facility

    International Nuclear Information System (INIS)

    Longhurst, G.R.

    1990-01-01

    The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.)

  8. The INEL Tritium Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R. (Idaho National Engineering Lab., Idaho Falls (USA))

    1990-06-01

    The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.).

  9. The regulation and licensing of research reactors and associated facilities in the United Kingdom

    International Nuclear Information System (INIS)

    Weightman, M.W.; Willby, C.R.

    1990-01-01

    In the United Kingdom, the Nuclear Installations Inspectorate (NII) licenses nuclear facilities, including research reactors, on behalf of the Health and Safety Executive (HSE). The legislation, the regulatory organizations and the methods of operation that have been developed over the last 30 years result in a largely non-prescriptive form of control that is well suited to research reactors. The most important part of the regulatory system is the license and the attachment of conditions which it permits. These conditions require the licensee to prepare arrangements to control the safety of the facility. In doing so the licensee is encouraged to develop a 'safety culture' within its organization. This is particularly important for research reactors which may have limited staff resources and where the ability, and at times the need, to have access to the core is much greater than for nuclear power plants. Present day issues such as the ageing of nuclear facilities, public access to the rationale behind regulatory decisions, and the emergence of more stringent safety requirements, which include a need for quantified safety criteria, have been addressed by the NII. This paper explores the relevance of such issues to the regulation of research reactors. In particular, it discusses some of the factors associated with research reactors that should be considered in developing criteria for the tolerability of risk from these nuclear facilities. From a consideration of these factors, it is the authors' view that the range of tolerable risk to the public from the operation of new research reactors may be expected to be more stringent than similar criteria for new nuclear power plants, whereas the criteria for tolerable risk for research reactor workers are expected to be about the same as those for power reactor workers

  10. Techniques for controlling air pollution from the operation of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    1966-03-01

    This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level. Refs, 24 figs, 5 tabs.

  11. Remotely operated facility for in situ solidification of fissile uranium

    International Nuclear Information System (INIS)

    McGinnis, C.P.; Collins, E.D.; Patton, B.D.

    1986-01-01

    A heavily shielded, remotely operated facility, located within the Radiochemical processing Plant at Oak Ridge National Laboratory (ORNL), has been designed and is being operated to convert approx.1000 kg of fissile uranium (containing approx.75% 235 U, approx.10% 233 U, and approx.140 ppM 232 U) from a nitrate solution (130 g of uranium per L) to a solid oxide form. This project, the Consolidated Edison Uranium Solidification Program (CEUSP), is being carried out in order to prepare a stable uranium form for longterm storage. This paper describes the solidification process selected, the equipment and facilities required, the experimental work performed to ensure successful operation, some problems that were solved, and the initial operations

  12. Operational status of nuclear facilities in Japan. 2008 edition

    International Nuclear Information System (INIS)

    2008-01-01

    This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2007 (from April 2007 to March 2008). I sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (J.P.N.)

  13. Operational status of nuclear facilities in Japan. 2010 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2009 (from April 2009 to March 2010). We sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (author)

  14. Licensing and Operations of the Clive, Utah Low-Level Containerized Radioactive Waste Disposal Facility- A Continuation of Excellence

    Energy Technology Data Exchange (ETDEWEB)

    Ledoux, M. R.; Cade, M. S.

    2002-02-25

    Envirocare's Containerized Waste Facility (CWF) is the first commercial low-level radioactive waste disposal facility to be licensed in the 21st century and the first new site to be opened and operated since the late 1970's. The licensing of this facility has been the culmination of over a decade's effort by Envirocare of Utah at their Clive, Utah site. With the authorization to receive and dispose of higher activity containerized Class A low-level radioactive waste (LLRW), this facility has provided critical access to disposal for the nuclear power industry, as well as the related research and medical communities. This paper chronicles the licensing history and operational efforts designed to address the disposal of containerized LLRW in accordance with state and federal regulations.

  15. Detailed description of an SSAC at the facility level for research reactors

    International Nuclear Information System (INIS)

    Jones, R.J.

    1984-09-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  16. Paul Scherrer Institute Scientific Report 1998. Volume VI: Large Research Facilities

    International Nuclear Information System (INIS)

    Bauer, Guenter; Bercher, Renate; Buechli, Carmen; Foroughi, Fereydoun; Meyer, Rosa

    1999-01-01

    The department GFA (Grossforschungsanlagen, Large Research Facilities) has been established in October 1998 and its main duty is operation, maintenance and development of the PSI accelerators, the spallation neutron source and the beam transport systems for pions and muons. A large effort of this group concerns the planning and co-ordination of the assembly of the Swiss Light Source (SLS). (author)

  17. Installation of the water environment irradiation facility for the IASCC research under the BWR/PWR irradiation environment (2)

    International Nuclear Information System (INIS)

    Magome, Hirokatsu; Okada, Yuji; Hanawa, Hiroshi; Sakuta, Yoshiyuki; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Shibata, Mitsunobu

    2014-07-01

    In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from 2012 to 2014 in the follow-up report reported before (JAEA-Technology 2013-019). (author)

  18. Safeguards systems analysis research and development and the practice of safeguards at DOE facilities

    International Nuclear Information System (INIS)

    Zack, N.R.; Thomas, K.E.; Markin, J.T.; Tape, J.W.

    1991-01-01

    Los Alamos Safeguards Systems Group personnel interact with Department of Energy (DOE) nuclear materials processing facilities in a number of ways. Among them are training courses, formal technical assistance such as developing information management or data analysis software, and informal ad hoc assistance especially in reviewing and commenting on existing facility safeguards technology and procedures. These activities are supported by the DOE Office of Safeguards and Security, DOE Operations Offices, and contractor organizations. Because of the relationships with the Operations Office and facility personnel, the Safeguards Systems Group research and development (R and D) staff have developed an understanding of the needs of the entire complex. Improved safeguards are needed in areas such as materials control activities, accountability procedures and techniques, systems analysis and evaluation methods, and material handling procedures. This paper surveys the generic needs for efficient and cost effective enhancements in safeguards technologies and procedures at DOE facilities, identifies areas where existing safeguards R and D products are being applied or could be applied, and sets a direction for future systems analysis R and D to address practical facility safeguards needs

  19. The NASA Lewis Research Center Internal Fluid Mechanics Facility

    Science.gov (United States)

    Porro, A. R.; Hingst, W. R.; Wasserbauer, C. A.; Andrews, T. B.

    1991-01-01

    An experimental facility specifically designed to investigate internal fluid duct flows is described. It is built in a modular fashion so that a variety of internal flow test hardware can be installed in the facility with minimal facility reconfiguration. The facility and test hardware interfaces are discussed along with design constraints of future test hardware. The plenum flow conditioning approach is also detailed. Available instrumentation and data acquisition capabilities are discussed. The incoming flow quality was documented over the current facility operating range. The incoming flow produces well behaved turbulent boundary layers with a uniform core. For the calibration duct used, the boundary layers approached 10 percent of the duct radius. Freestream turbulence levels at the various operating conditions varied from 0.64 to 0.69 percent of the average freestream velocity.

  20. Operation technology of air treatment system in nuclear facilities

    CERN Document Server

    Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

    2001-01-01

    Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

  1. Operating experience and radiation protection problems in the working of the radio-metallurgy hot cell facilities at BARC

    International Nuclear Information System (INIS)

    Janardhanan, S.; Watamwar, S.B.; Mehta, S.K.; Pillai, P.M.B.; John, Jacob; Kutty, K.N.

    1977-01-01

    The Bhabha Atomic Research Centre at Bombay has six hot cell facilities for radiometallurgical investigations of irradiated/failed fuel elements. The hot cell facilities have been provided with certain built-in safety features, a ventilation system, radiation monitoring instruments for various purposes, a centralised air monitoring system and a central panel for display of various alarms. Procedures adopted for radiation protection and contamination control include : (1) radiation leak test for cells and filter efficiency evaluation before cell activation, (2) practices to be followed by frog suit personnel while working in hot cell areas, (3) receipt and handling of irradiated fuel elements, (4) cell filter change operation, (5) checks on high level drains and (6) effluent discharge and waste shipments. Operating experience in the working of these facilities along with radiation accident incidents is described. Data regarding release of activity during normal cell operations, dose rates during various metallurgical operations and personnel exposures are presented. (M.G.B.)

  2. The insertion device magnetic measurement facility: Prototype and operational procedures

    International Nuclear Information System (INIS)

    Burkel, L.; Dejus, R.; Maines, J.; O'Brien, J.; Vasserman, I.; Pfleuger, J.

    1993-03-01

    This report is a description of the current status of the magnetic measurement facility and is a basic instructional manual for the operation of the facility and its components. Please refer to the appendices for more detailed information about specific components and procedures. The purpose of the magnetic measurement facility is to take accurate measurements of the magnetic field in the gay of the IDs in order to determine the effect of the ID on the stored particle beam and the emitted radiation. The facility will also play an important role when evaluating new ideas, novel devices, and inhouse prototypes as part of the ongoing research and development program at the APS. The measurements will be performed with both moving search coils and moving Hall probes. The IDs will be evaluated by computer modeling of the emitted radiation for any given (measured) magnetic field map. The quality of the magnetic field will be described in terms of integrated multipoles for the effect on Storage Ring performance and in terms of the derived trajectories for the emitted radiation. Before being installed on the Storage Ring, every device will be measured and characterized to assure that it is compatible with Storage Ring requirements and radiation specifications. The accuracy that the APS needs to achieve for magnetic measurements will be based on these specifications

  3. Facility management research in the Netherlands

    NARCIS (Netherlands)

    Thijssen, Thomas; van der Voordt, Theo; Mobach, Mark P.

    This article provides a brief overview of the history and development of facility management research in the Netherlands and indicates future directions. Facility management as a profession has developed from single service to multi-services and integral services over the past 15 years.

  4. First Materials Science Research Facility Rack Capabilities and Design Features

    Science.gov (United States)

    Cobb, S.; Higgins, D.; Kitchens, L.; Curreri, Peter (Technical Monitor)

    2002-01-01

    The first Materials Science Research Rack (MSRR-1) is the primary facility for U.S. sponsored materials science research on the International Space Station. MSRR-1 is contained in an International Standard Payload Rack (ISPR) equipped with the Active Rack Isolation System (ARIS) for the best possible microgravity environment. MSRR-1 will accommodate dual Experiment Modules and provide simultaneous on-orbit processing operations capability. The first Experiment Module for the MSRR-1, the Materials Science Laboratory (MSL), is an international cooperative activity between NASA's Marshall Space Flight Center (MSFC) and the European Space Agency's (ESA) European Space Research and Technology Center (ESTEC). The MSL Experiment Module will accommodate several on-orbit exchangeable experiment-specific Module Inserts which provide distinct thermal processing capabilities. Module Inserts currently planned for the MSL are a Quench Module Insert, Low Gradient Furnace, and a Solidification with Quench Furnace. The second Experiment Module for the MSRR-1 configuration is a commercial device supplied by MSFC's Space Products Development (SPD) Group. Transparent furnace assemblies include capabilities for vapor transport processes and annealing of glass fiber preforms. This Experiment Module is replaceable on-orbit. This paper will describe facility capabilities, schedule to flight and research opportunities.

  5. Experiments, conceptual design, preliminary cost estimates and schedules for an underground research facility

    International Nuclear Information System (INIS)

    Korbin, G.; Wollenberg, H.; Wilson, C.; Strisower, B.; Chan, T.; Wedge, D.

    1981-09-01

    Plans for an underground research facility are presented, incorporating techniques to assess the hydrological and thermomechanical response of a rock mass to the introduction and long-term isolation of radioactive waste, and to assess the effects of excavation on the hydrologic integrity of a repository and its subsequent backfill, plugging, and sealing. The project is designed to utilize existing mine or civil works for access to experimental areas and is estimated to last 8 years at a total cost for contruction and operation of $39.0 million (1981 dollars). Performing the same experiments in an existing underground research facility would reduce the duration to 7-1/2 years and cost $27.7 million as a lower-bound estimate. These preliminary plans and estimates should be revised after specific sites are identified which would accommodate the facility

  6. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    International Nuclear Information System (INIS)

    Ballinger, M.Y.; Shields, K.D.

    1999-01-01

    The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP

  7. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ballinger, M.Y.; Shields, K.D.

    1999-04-02

    The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP.

  8. Nanotechnology on a dime: building affordable research facilities

    Science.gov (United States)

    DiBattista, Jeff; Clare, Donna; Lynch, David

    2005-08-01

    Designing buildings to house nanotechnology research presents a multitude of well-recognized challenges to architectural and engineering design teams, from environmental control to spatial arrangements to operational functionality. These technical challenges can be solved with relative ease on projects with large budgets: designers have the option of selecting leading-edge systems without undue regard for their expense. This is reflected in the construction cost of many nanotechnology research facilities that run well into the hundreds of millions of dollars. Smaller universities and other institutions need not be shut out of the nanotechnology research field simply because their construction budgets are tens of millions of dollars or less. The key to success for these less expensive projects lies with making good strategic decisions: identifying priorities for the facility in terms of what it will is--and will not--provide to the researchers. Making these strategic decisions puts bounds on the tactical, technical problems that the design team at large must address, allowing them to focus their efforts on the key areas for success. The process and challenges of this strategic decision-making process are examined, with emphasis placed on the types of decisions that must be made and the factors that must be considered when making them. Case study examples of projects undertaken at the University of Alberta are used to illustrate how strategic-level decision-making sets the stage for cutting-edge success on a modest budget.

  9. Radiation protection -Operation of chemical wastewater treatment facility

    International Nuclear Information System (INIS)

    Lee, M. J.; Lim, M. H.; Ahn, S. S.; Jeong, Y. S.

    1996-12-01

    The wastewater and sewage treatment facility have been operated. From the results of operation, it was confirmed that the quality of treated wastewater was 1/5 or 1/10 lower than that of regulation of law for environmental conservation. The quality of treated sewage has been maintained to 70% of regulation of law for environmental conservation. (author). 14 tabs., 8 figs

  10. An Overview of the Microgravity Science Glovebox (MSG) Facility and the Research Performed in the MSG on the International Space Station (ISS)

    Science.gov (United States)

    Jordan, Lee P.

    2013-01-01

    The Microgravity Science Glovebox (MSG) is a rack facility aboard the International Space Station (ISS) designed for investigation handling. The MSG was built by the European Space Agency (ESA) which also provides sustaining engineering support for the facility. The MSG has been operating on the ISS since July 2002 and is currently located in the US Laboratory Module. The unique design of the facility allows it to accommodate science and technology investigations in a "workbench" type environment. The facility has an enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for small parts, particulates, fluids, and gases. This containment approach protects the crew from possible hazardous operations that take place inside the MSG work volume. Research investigations operating inside the MSG are provided a large 255 liter enclosed work space, 1000 watts of dc power via a versatile supply interface (120, 28, +/- 12, and 5 Vdc), 1000 watts of cooling capability, video and data recording and real time downlink, ground commanding capabilities, access to ISS Vacuum Exhaust and Vacuum Resource Systems, and gaseous nitrogen supply. These capabilities make the MSG one of the most utilized facilities on ISS. The MSG has been used for over 14500 hours of scientific payload operations. MSG investigations involve research in cryogenic fluid management, fluid physics, spacecraft fire safety, materials science, combustion, plant growth, and life support technology. The MSG facility is operated by the Payloads Operations Integration Center at Marshall Space flight Center. Payloads may also operate remotely from different telescience centers located in the United States and Europe. The investigative Payload Integration Manager (iPIM) is the focal to assist organizations that have payloads operating in the MSG facility. NASA provides an MSG engineering unit for payload developers

  11. Establishment of the Neutron Beam Research Facility at the OPAL Reactor

    International Nuclear Information System (INIS)

    Kennedy, S.J.; Robinson, R.A.

    2012-01-01

    Full text: Australia's first research reactor, HIFAR, reached criticality in January 1958. At that time Australia's main agenda was establishment of a nuclear power program. HIFAR operated for nearly 50 years, providing a firm foundation for the establishment of Australia's second generation research Reactor OPAL, which reached criticality in August 006. In HIFAR's early years a neutron beam facility was established for materials characterization, partly in aid of the nuclear energy agenda and partly in response to interest from Australia's scientific community. By the time Australia's nuclear energy program ceased (in the 1970s), radioisotope production and research had also been established at Lucas Heights. Also, by this time the neutron beam facility for scientific research had evolved into a major utilization programme, warranting establishment of an independent body to facilitate scientific access (the Australian Institute for Nuclear Science and Engineering). In HIFAR's lifetime, ANSTO established a radiopharmaceuticals service for the Australian medical community and NDT silicon production was also established and grew to maturity. So when time came to determine the strategy for nuclear research in Australia into the 21st century, it was clear that the replacement for HIFAR should be multipurpose, with major emphases on scientific applications of neutron beams and medical isotope production. With this strategy in mind, ANSTO set about to design and build OPAL with a world-class neutron beam facility, capable of supporting a large and diverse scientific research community. The establishment of the neutron beam facility became the mission of the Bragg Institute management team. This journey began in 1997 with establishment of a working budget, and reached its first major objective when OPAL reached 20 MW thermal power nearly one decade later (in 2006). The first neutron beam instruments began operation soon after (in 2007), and quickly proved themselves to be

  12. Umatilla hatchery satellite facilities operation and maintenance. Annual report 1996

    International Nuclear Information System (INIS)

    Rowan, G.D.

    1997-06-01

    The Confederated Tribes of the Umatilla Indian Reservation (CTUIR) and Oregon Department of Fish and Wildlife (ODFW) are cooperating in a joint effort to enhance steelhead and re-establish salmon runs in the Umatilla River Basin. As an integral part of this program, Bonifer Pond, Minthorn Springs, Imeques C-mem-ini-kem and Thornhollow satellite facilities are operated for acclimation and release of juvenile summer steelhead (Oncorhynchus mykiss), fall and spring chinook salmon (O. tshawytscha) and coho salmon (O. kisutch). Minthorn is also used for holding and spawning adult summer steelhead and Three Mile Dam is used for holding and spawning adult fall chinook and coho salmon. Bonifer, Minthorn, Imeques and Thornhollow facilities are operated for acclimation and release of juvenile salmon and summer steelhead. The main goal of acclimation is to reduce stress from trucking prior to release and improve imprinting of juvenile salmonids in the Umatilla River Basin. Juveniles are transported to the acclimation facilities primarily from Umatilla and Bonneville Hatcheries. This report details activities associated with operation and maintenance of the Bonifer, Minthorn, Imeques, Thornhollow and Three Mile Dam facilities in 1996

  13. APET methodology for Defense Waste Processing Facility: Mode C operation

    International Nuclear Information System (INIS)

    Taylor, R.P. Jr.; Massey, W.M.

    1995-04-01

    Safe operation of SRS facilities continues to be the highest priority of the Savannah River Site (SRS). One of these facilities, the Defense Waste Processing Facility or DWPF, is currently undergoing cold chemical runs to verify the design and construction preparatory to hot startup in 1995. The DWPFF is a facility designed to convert the waste currently stored in tanks at the 200-Area tank farm into a form that is suitable for long term storage in engineered surface facilities and, ultimately, geologic isolation. As a part of the program to ensure safe operation of the DWPF, a probabilistic Safety Assessment of the DWPF has been completed. The results of this analysis are incorporated into the Safety Analysis Report (SAR) for DWPF. The usual practice in preparation of Safety Analysis Reports is to include only a conservative analysis of certain design basis accidents. A major part of a Probabilistic Safety Assessment is the development and quantification of an Accident Progression Event Tree or APET. The APET provides a probabilistic representation of potential sequences along which an accident may progress. The methodology used to determine the risk of operation of the DWPF borrows heavily from methods applied to the Probabilistic Safety Assessment of SRS reactors and to some commercial reactors. This report describes the Accident Progression Event Tree developed for the Probabilistic Safety Assessment of the DWPF

  14. New requirements to collect operational data that are essential for facility decommissioning

    International Nuclear Information System (INIS)

    Kristofova, K.; Valcuha, P.

    2017-01-01

    The paper describes the features of the first nuclear regulatory safety guide to be released by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in field of decommissioning. This safety guide specifies requirements to collect those nuclear facility operational data that are essential for its decommissioning. Recommendations of international organisations as well as experience in selected countries are provided. The following operational data types necessary for decommissioning process are identified and analysed: design documentation including modifications and changes during operation, photo-documentation, operational events and material and radiological inventory of the nuclear facility. The guide establishes requirements for collection of the operational data that can be recorded in interconnected database modules. In addition, a structure of decommissioning database is proposed, representing material and radiological inventory of a nuclear facility. This inventory database forms a basis for planning of the decommissioning process. At last, the guide summarises recommendations for data collection, archiving and maintenance of database records and also their applications in safety documentation necessary for decommissioning of nuclear facilities in Slovakia. (authors)

  15. Maintenance, operation, and research (radiation) zones (MORZ) application model - a design and operation tool for intelligent buildings with application to the advanced neutron source

    International Nuclear Information System (INIS)

    Shapira, H.B.; Brown, R.A.

    1995-01-01

    This paper describes a user-friendly application tool to assist in the design, operation and maintenance of large buildings/facilities charged with complex/extensive/elaborate activities. The model centers around a specially designed, easy-access data base containing essentially all the relevant information about the facility. Our first test case is the Advanced Neutron Source (ANS) research reactor to be constructed as a center for neutron research

  16. Air emission points for facilities in Iowa with operating permits for Title V of the Federal Clean Air Act_considered MAJOR permits

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Air emission points for facilities in Iowa with operating permits for Title V of the Federal Clean Air Act, considered "major" permits. Also includes emission points...

  17. MagLev Cobra: Test Facilities and Operational Experiments

    International Nuclear Information System (INIS)

    Sotelo, G G; Dias, D H J N; De Oliveira, R A H; Ferreira, A C; De Andrade, R Jr; Stephan, R M

    2014-01-01

    The superconducting MagLev technology for transportation systems is becoming mature due to the research and developing effort of recent years. The Brazilian project, named MagLev-Cobra, started in 1998. It has the goal of developing a superconducting levitation vehicle for urban areas. The adopted levitation technology is based on the diamagnetic and the flux pinning properties of YBa 2 Cu 3 O 7−δ (YBCO) bulk blocks in the interaction with Nd-Fe-B permanent magnets. A laboratory test facility with permanent magnet guideway, linear induction motor and one vehicle module is been built to investigate its operation. The MagLev-Cobra project state of the art is presented in the present paper, describing some construction details of the new test line with 200 m.

  18. Annual Report of Radioactive Waste Facilities Operation in 2015

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; GAO; Zhi-gang; DIAO; Lei; SHEN; Zheng; LI; Wen-ge

    2015-01-01

    301of the Department of Radiochemistry,is in charge of the management of radioactive waste and the safety of the relative facilities to meet the request of the scientific research production.There are 16radioactive waste facilities,including9facilities which are closed and monitored

  19. An economic benefit analysis on the cobalt-60 irradiation facility of Beijing Radiation Research Center

    International Nuclear Information System (INIS)

    Wang Binlin

    1995-01-01

    The peculiarity, the investment and annual operating cost of the 3.7 x 10 16 Bq (MCi) cobalt-60 irradiation facility at Beijing Radiation Application Research Centre are described. Its economic benefits each year are analyzed according to several year operating practice. Some related questions on carrying out radiation processing are raised and discussed. (author)

  20. Materials Engineering Research Facility (MERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s Materials Engineering Research Facility (MERF) enables engineers to develop manufacturing processes for producing advanced battery materials in sufficient...

  1. Paul Scherrer Institute Scientific Report 1998. Volume VI: Large Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, Guenter; Bercher, Renate; Buechli, Carmen; Foroughi, Fereydoun; Meyer, Rosa [eds.

    1999-09-01

    The department GFA (Grossforschungsanlagen, Large Research Facilities) has been established in October 1998 and its main duty is operation, maintenance and development of the PSI accelerators, the spallation neutron source and the beam transport systems for pions and muons. A large effort of this group concerns the planning and co-ordination of the assembly of the Swiss Light Source (SLS). (author) figs., tabs., refs.

  2. Operational Readiness Review: Savannah River Replacement Tritium Facility

    International Nuclear Information System (INIS)

    1993-02-01

    The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members

  3. Safety of research reactors (Design and Operation)

    International Nuclear Information System (INIS)

    Dirar, H. M.

    2012-06-01

    The primary objective of this thesis is to conduct a comprehensive up-to-date literature review on the current status of safety of research reactor both in design and operation providing the future trends in safety of research reactors. Data and technical information of variety selected historical research reactors were thoroughly reviewed and evaluated, furthermore illustrations of the material of fuel, control rods, shielding, moderators and coolants used were discussed. Insight study of some historical research reactors was carried with considering sample cases such as Chicago Pile-1, F-1 reactor, Chalk River Laboratories,. The National Research Experimental Reactor and others. The current status of research reactors and their geographical distribution, reactor category and utilization is also covered. Examples of some recent advanced reactors were studied like safety barriers of HANARO of Korea including safety doors of the hall and building entrance and finger print identification which prevent the reactor from sabotage. On the basis of the results of this research, it is apparent that a high quality of safety of nuclear reactors can be attained by achieving enough robust construction, designing components of high levels of efficiency, replacing the compounds of the reactor in order to avoid corrosion and degradation with age, coupled with experienced scientists and technical staffs to operate nuclear research facilities.(Author)

  4. A research on threat (hazard) categorization method for nuclear facilities

    International Nuclear Information System (INIS)

    Tang Rongyao; Xu Xiaoxiao; Zhang Jiangang; Zhao Bin; Wang Xuexin

    2011-01-01

    The threat categorization method suggested by International Atomic Energy Agency (IAEA) and hazard categorization standard by the Department of Energy of United States (USDOE) for nuclear facilities are compared and discussed in this paper. The research shows the two types of categorization method for nuclear facilities are similar, though each has its own specialty. The categorization method suggested by IAEA for the purpose of emergency planning is quite completed and updated. The categorization method of DOE is advanced in its operability, and fits for safety surveillance. But the dispersible radioactive material thresholds used for categorization need to be updated. The threshold of category 3 is somewhat disputable for many reasons. The recommended categorization method for China is also given in this paper. (author)

  5. Operation of a low-level waste disposal facility and how to prevent problems in future facilities

    International Nuclear Information System (INIS)

    Di Sibio, R.

    1985-01-01

    Operation of a low-level waste facility is an ever increasing problem nationally, and specifically one that could grow to crisis proportion in Pennsylvania. There have been, nevertheless, a variety of changes over the years in the management of low level radioactive waste, particularly with regard to disposal facilities that can avert a crisis condition. A number of companies have been organized thru possible a broad range of services to the nuclear industry, including those that emphasize solidification of waste materials, engineering services, waste management, and transportation to disposal sites across the United States. This paper addresses one particular site and the problems which evolved at that site from an environmental perspective. It is important that it is clearly understood that, although these problems are resolvable, the lessons learned here are critical for the prevention of problems at future facilities. The focus of this paper is on the Maxey Flats, Kentucky disposal facility which was closed in 1977. It must be understood that the regulations for siting, management, burial techniques, waste classification, and the overall management of disposal sites were limited when this facility was in operation

  6. Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

    Energy Technology Data Exchange (ETDEWEB)

    Tyner, C.J.; Birk, S.M.

    1995-09-01

    This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs.

  7. Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

    International Nuclear Information System (INIS)

    Tyner, C.J.; Birk, S.M.

    1995-09-01

    This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs

  8. Reference equilibrium core with central flux irradiation facility for Pakistan research reactor-1

    International Nuclear Information System (INIS)

    Israr, M.; Shami, Qamar-ud-din; Pervez, S.

    1997-11-01

    In order to assess various core parameters a reference equilibrium core with Low Enriched Uranium (LEU) fuel for Pakistan Research Reactor (PARR-1) was assembled. Due to increased volume of reference core, the average neutron flux reduced as compared to the first higher power operation. To get a higher neutron flux an irradiation facility was created in centre of the reference equilibrium core where the advantage of the neutron flux peaking was taken. Various low power experiments were performed in order to evaluate control rods worth and neutron flux mapping inside the core. The neutron flux inside the central irradiation facility almost doubled. With this arrangement reactor operation time was cut down from 72 hours to 48 hours for the production of the required specific radioactivity. (author)

  9. Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

    International Nuclear Information System (INIS)

    Salazar, M.D.

    1998-01-01

    Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel

  10. Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.D.

    1998-12-01

    Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel.

  11. Operation of the Nuclear Radiation Center as an all-university facility

    International Nuclear Information System (INIS)

    Hinman, G.W.

    1972-01-01

    The TRIGA at WSU is part of an all university research unit and its structure and work organization are presented. The facility seeks users from the university and from outside the university. In many cases projects are jointly sponsored by NRC faculty together with faculty from elsewhere on campus. In other cases neutrons or free use of other equipment is provided. The promotional efforts are rather sharply focused on environmental and health related problems. The effects of the institutional arrangement on the operation of the Centre are discussed

  12. Environmental analysis of the operation of the ERDA facilities in Oak Ridge

    International Nuclear Information System (INIS)

    McWherter, J.R.

    1975-01-01

    An analysis of the environmental effects of current ERDA operations in Oak Ridge is being conducted to establish a baseline for the consideration of the environmental effects of additional facilities or modified operations in the future. An extensive ecological survey has been conducted for about one year; social and economic data were obtained; and an archaeological survey of the area was made. The facilities were described and the effluents associated with operations were quantified to the extent practical. The effects of effluent releases to the environment are being analyzed. The social effects of the ERDA facilities in Oak Ridge are also being studied. (auth)

  13. Visitor’s Guide to Oliktok Point Atmospheric Radiation Measurement Climate Research Facility, North Slope of Alaska

    Energy Technology Data Exchange (ETDEWEB)

    Desilets, Darin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Helsel, Fred M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bendure, Al O. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lucero, Daniel A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ivey, Mark D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dexheimer, Danielle N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-04-01

    The importance of Oliktok Point, Alaska, as a focal point for climate research in the Arctic continues to grow with the addition of a U.S. Department of Energy (DOE) Atmospheric Radiation Monitoring (ARM) Climate Research Facility Mobile Facility (AMF) and the expansion of infrastructure to support airborne measurements. The site hosts a suite of instruments for making multi-year, high-fidelity atmospheric measurements; serves as a base of operations for field campaigns; and contains the only Restricted Airspace and Warning Area in the U.S. Arctic, which enables the use of unmanned aircraft systems. The use of this site by climate researchers involves several considerations, including its remoteness, harsh climate, and location amid the North Slope oilfields. This guide is intended to help visitors to Oliktok Point navigate this unique physical and administrative environment, and thereby facilitate safe and productive operations.

  14. Retention-tank systems: A unique operating practice for managing complex waste streams at research and development facilities

    International Nuclear Information System (INIS)

    Brigdon, S.

    1996-01-01

    The importance of preventing the introduction of prohibited contaminants to the sanitary sewer is critical to the management of large federal facilities such as the Lawrence Livermore National Laboratory (LLNL). LLNL operates 45 retention-tank systems to control wastewater discharges and to maintain continued compliance with environmental regulations. LLNL's unique internal operation practices successfully keep prohibited contaminants out of the sanitary waste stream and maintain compliance with federal, state, and local regulations, as well as determining appropriate wastewater-disposal options. Components of the system include sampling and analysis of the waste stream, evaluation of the data, discharge approval, and final disposition of the waste stream

  15. Manual for operation of the multipurpose thermalhydraulic test facility TOPFLOW (Transient Two Phase Flow Test Facility)

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schuetz, H.; Pietruske, H.; Lenk, S.

    2004-07-01

    The Forschungszentrum Rossendorf (FZR) e. V. is constructing a new large-scale test facility, TOPFLOW, for thermalhydraulic single effect tests. The acronym stands for transient two phase flow test facility. It will mainly be used for the investigation of generic and applied steady state and transient two phase flow phenomena and the development and validation of models of computational fluid dynamic (CFD) codes. The manual of the test facility must always be available for the staff in the control room and is restricted condition during operation of personnel and also reconstruction of the facility. (orig./GL)

  16. Operational Research : Congress of APDIO, the Portuguese Operational Research Society

    CERN Document Server

    Almeida, João; Oliveira, José; Pinto, Alberto

    2018-01-01

    This proceedings book presents selected contributions from the XVIII Congress of APDIO (the Portuguese Association of Operational Research) held in Valença on June 28–30, 2017. Prepared by leading Portuguese and international researchers in the field of operations research, it covers a wide range of complex real-world applications of operations research methods using recent theoretical techniques, in order to narrow the gap between academic research and practical applications. Of particular interest are the applications of, nonlinear and mixed-integer programming, data envelopment analysis, clustering techniques, hybrid heuristics, supply chain management, and lot sizing and job scheduling problems. In most chapters, the problems, methods and methodologies described are complemented by supporting figures, tables and algorithms.   The XVIII Congress of APDIO marked the 18th installment of the regular biannual meetings of APDIO – the Portuguese Association of Operational Research. The meetings bring toget...

  17. Engine Environment Research Facility (EERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility supports research and development testing of the behavior of turbine engine lubricants, fuels and sensors in an actual engine environment....

  18. Metering management at the plutonium research and development facilities

    International Nuclear Information System (INIS)

    Hirata, Masaru; Miyamoto, Fujio; Kurosawa, Makoto; Abe, Jiro; Sakai, Haruyuki; Suzuki, Tsuneo.

    1996-01-01

    Nuclear fuel research laboratory of the Oarai Research Laboratory of the Japan Atomic Energy Research Institute is an R and D facility to treat with plutonium and processes various and versatile type samples in chemical and physical form for use of various experimental researches even though on much small amount. Furthermore, wasted and plutonium samples are often transported to other KMP and MBA such as radioactive waste management facility, nuclear reactor facility and so forth. As this facility is a place to treat plutonium important on the safeguards, it is a facility necessary for detection and allowance actions and for detail managements on the metering management data to report to government and IAEA in each small amount sample and different configuration. In this paper, metering management of internationally regulated matters and metering management system using a work station newly produced in such small scale facility were introduced. (G.K.)

  19. Detonation Engine Research Facility (DERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility is configured to safely conduct experimental pressuregain combustion research. The DERF is capable of supporting up to 60,000 lbf thrust...

  20. The neutron beam facility at the Australian replacement research reactor

    International Nuclear Information System (INIS)

    Hunter, B.; Kennedy, S.

    1999-01-01

    Full text: The Australian federal government gave ANSTO final approval to build a research reactor to replace HIFAR on August 25th 1999. The replacement reactor is to be a multipurpose reactor with a thermal neutron flux of 3 x 10 14 n.cm -2 .s -1 and having improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The replacement reactor will commence operation in 2005 and will cater for Australian scientific, industrial and medical needs well into the 21st century. The scientific capabilities of the neutron beams at the replacement reactor are being developed in consultation with representatives from academia, industry and government research laboratories to provide a facility for condensed matter research in physics, chemistry, materials science, life sciences, engineering and earth sciences. Cold, thermal and hot neutron sources are to be installed, and neutron guides will be used to position most of the neutron beam instruments in a neutron guide hall outside the reactor confinement building. Eight instruments are planned for 2005, with a further three to be developed by 2010. A conceptual layout for the neutron beam facility is presented including the location of the planned suite of neutron beam instruments. The reactor and all the associated infrastructure, with the exception of the neutron beam instruments, is to be built by an accredited reactor builder in a turnkey contract. Tenders have been called for December 1999, with selection of contractor planned by June 2000. The neutron beam instruments will be developed by ANSTO and other contracted organisations in consultation with the user community and interested overseas scientists. The facility will be based, as far as possible, around a neutron guide hall that is be served by three thermal and three cold neutron guides. Efficient transportation of thermal and cold neutrons to the guide hall requires the use of modern super

  1. Annual report of Department of Research Reactor and Tandem Accelerator, JFY2012. Operation, utilization and technical development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

    International Nuclear Information System (INIS)

    Murayama, Yoji; Ishii, Tetsuro; Nakamura, Kiyoshi; Uno, Yuki; Ishikuro, Yasuhiro; Kawashima, Kazuhito; Ishizaki, Nobuhiro; Matsumura, Taichi; Nagahori, Kazuhisa; Odauchi, Shouji; Maruo, Takeshi

    2014-03-01

    The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3(Japan Research Reactor No.3), JRR-4(Japan Research Reactor No.4), NSRR(Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes a summary of activities of services and technical developments carried out in the period between April 1, 2012 and March 31, 2013. The activities were categorized into five service/development fields: (1) Operation and maintenance of research reactors and tandem accelerator, (2) Utilization of research reactors and tandem accelerator, (3) Upgrading of utilization techniques of research reactors and tandem accelerator, (4) Safety administration for department of research reactor and tandem accelerator, (5) International cooperation. Also contained are lists of publications, meetings, granted permissions on laws and regulations concerning atomic energy, number of staff members dispatched to Fukushima for the technical assistance, outcomes in service and technical developments and so on. (author)

  2. Experience in startup and operation of fast flux facility

    International Nuclear Information System (INIS)

    Moffitt, W.C.

    1980-01-01

    The testing program was structured to perform all testing under formal testing procedures with a test engineer as the test director and the plant operators operating the systems and equipment. This provided excellent training and experience for the operators in preparation for eventual reactor operation. Operations preparations for the testing and operation activities has consisted of academic training, formal on-the-job training including systems operation and examinations by persons with an expert knowledge on that portion of the plant, training at EBR-II and the High Temperature Sodium Facility for selected senior operators, operating procedure preparation, training on an FFTF Control Room operator training simulator, and formal written, oral and operating examinations

  3. Impact of proposed research reactor standards on reactor operation

    Energy Technology Data Exchange (ETDEWEB)

    Ringle, J C; Johnson, A G; Anderson, T V [Oregon State University (United States)

    1974-07-01

    A Standards Committee on Operation of Research Reactors, (ANS-15), sponsored by the American Nuclear Society, was organized in June 1971. Its purpose is to develop, prepare, and maintain standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training. Of the 15 original members, six were directly associated with operating TRIGA facilities. This committee developed a standard for the Development of Technical Specifications for Research Reactors (ANS-15.1), the revised draft of which was submitted to ANSI for review in May of 1973. The Committee then identified 10 other critical areas for standards development. Nine of these, along with ANS-15.1, are of direct interest to TRIGA owners and operators. The Committee was divided into subcommittees to work on these areas. These nine areas involve proposed standards for research reactors concerning: 1. Records and Reports (ANS-15.3) 2. Selection and Training of Personnel (ANS-15.4) 3. Effluent Monitoring (ANS-15.5) 4. Review of Experiments (ANS-15.6) 5. Siting (ANS-15.7) 6. Quality Assurance Program Guidance and Requirements (ANS-15.8) 7. Restrictions on Radioactive Effluents (ANS-15.9) 8. Decommissioning (ANS-15.10) 9. Radiological Control and Safety (ANS-15.11). The present status of each of these standards will be presented, along with their potential impact on TRIGA reactor operation. (author)

  4. Impact of proposed research reactor standards on reactor operation

    International Nuclear Information System (INIS)

    Ringle, J.C.; Johnson, A.G.; Anderson, T.V.

    1974-01-01

    A Standards Committee on Operation of Research Reactors, (ANS-15), sponsored by the American Nuclear Society, was organized in June 1971. Its purpose is to develop, prepare, and maintain standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training. Of the 15 original members, six were directly associated with operating TRIGA facilities. This committee developed a standard for the Development of Technical Specifications for Research Reactors (ANS-15.1), the revised draft of which was submitted to ANSI for review in May of 1973. The Committee then identified 10 other critical areas for standards development. Nine of these, along with ANS-15.1, are of direct interest to TRIGA owners and operators. The Committee was divided into subcommittees to work on these areas. These nine areas involve proposed standards for research reactors concerning: 1. Records and Reports (ANS-15.3) 2. Selection and Training of Personnel (ANS-15.4) 3. Effluent Monitoring (ANS-15.5) 4. Review of Experiments (ANS-15.6) 5. Siting (ANS-15.7) 6. Quality Assurance Program Guidance and Requirements (ANS-15.8) 7. Restrictions on Radioactive Effluents (ANS-15.9) 8. Decommissioning (ANS-15.10) 9. Radiological Control and Safety (ANS-15.11). The present status of each of these standards will be presented, along with their potential impact on TRIGA reactor operation. (author)

  5. Environmental aspects based on operation performance of nuclear fuel fabrication facilities

    International Nuclear Information System (INIS)

    2001-07-01

    This publication was prepared within the framework of the IAEA Project entitled Development and Upgrading of Guidelines, Databases and Tools for Integrating Comparative Assessment into Energy System Analysis and Policy Making, which included the collection, review and input of data into a database on health and environmental impacts related to operation of nuclear fuel cycle facilities. The objectives of the report included assembling environmental data on operational performance of nuclear fabrication facilities in each country; compiling and arranging the data in a database, which will be easily available to experts and the public; and presenting data that may be of value for future environmental assessment of nuclear fabrication facilities

  6. Regulatory Approach to Safety of Long Time Operating Research Reactors in Russia

    Energy Technology Data Exchange (ETDEWEB)

    Sapozhnikov, Alexander [Industrial and Nuclear Supervision Service, Moscow (Russian Federation)

    2013-07-01

    In the Russian Federation more than 60% of operating Nuclear Research Facilities (NRFs) are of age over 30 years old or their usage exceeds originally conceived continuous operation. In this regard, important areas of regulatory body activity are: 1) a systematic assessment of the actual state of structures, systems and components (SSCs) important to safety, 2) control of implementation of organizational and technical measures to mitigate ageing impact on the basis of programmes to manage reliability (service life) of SSCs, and 3) issues of facility modification/reconstruction in line with up-to-day safety requirements. The practice of licensing NRFs with long operating times shows that the national regulations are generally in compliance with IAEA recommendations for ageing management of research reactors. In operating organizations, the ageing management is being effectively provided as a part of the integrated management system for NRFs, including the monitoring of the reliability of SSCs, a methodology to detect their ageing, reporting and investigation of events, analysis of their root causes, and measures to prevent and mitigate ageing effects to safety. The report outlines a good practice of safety regulation of NRFs with long operating times and based on lessons learned from experience, including challenges for future improvement of ageing management.

  7. Regulatory Approach to Safety of Long Time Operating Research Reactors in Russia

    International Nuclear Information System (INIS)

    Sapozhnikov, Alexander

    2013-01-01

    In the Russian Federation more than 60% of operating Nuclear Research Facilities (NRFs) are of age over 30 years old or their usage exceeds originally conceived continuous operation. In this regard, important areas of regulatory body activity are: 1) a systematic assessment of the actual state of structures, systems and components (SSCs) important to safety, 2) control of implementation of organizational and technical measures to mitigate ageing impact on the basis of programmes to manage reliability (service life) of SSCs, and 3) issues of facility modification/reconstruction in line with up-to-day safety requirements. The practice of licensing NRFs with long operating times shows that the national regulations are generally in compliance with IAEA recommendations for ageing management of research reactors. In operating organizations, the ageing management is being effectively provided as a part of the integrated management system for NRFs, including the monitoring of the reliability of SSCs, a methodology to detect their ageing, reporting and investigation of events, analysis of their root causes, and measures to prevent and mitigate ageing effects to safety. The report outlines a good practice of safety regulation of NRFs with long operating times and based on lessons learned from experience, including challenges for future improvement of ageing management

  8. Operation of the hot test loop facilities

    International Nuclear Information System (INIS)

    Cheong, Moon Ki; Park, Choon Kyeong; Won, Soon Yeon; Yang, Sun Kyu; Cheong, Jang Whan; Cheon, Se Young; Song, Chul Hwa; Jeon, Hyeong Kil; Chang, Suk Kyu; Jeong, Heung Jun; Cho, Young Ro; Kim, Bok Duk; Min, Kyeong Ho

    1994-12-01

    The objective of this project is to obtain the available experimental data and to develop the measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics department have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within fuel bundle and to understand the characteristic of pressure drop required for improving the nuclear fuel and to develop the advanced measuring techniques. RCS Loop, which is used to measure the CHF, is presently under design and construction. B and C Loop is designed and constructed to assess the automatic depressurization safety system behavior. 4 tabs., 79 figs., 7 refs. (Author) .new

  9. Operation and utilization of low power research reactor critical facility for Advanced Heavy Water Reactor (AHWR)

    International Nuclear Information System (INIS)

    De, S.K.; Karhadkar, C.G.

    2017-01-01

    An Advanced Heavy Water Reactor (AHWR) has been designed and developed for maximum power generation from thorium considering large reserves of thorium. The design envisages using 54 pin MOX cluster with different enrichment of "2"3"3U and Pu in Thoria fuel pins. Theoretical models developed to neutron transport and the geometrical details of the reactor including all reactivity devices involve approximations in modelling, resulting in uncertainties. With a view to minimize these uncertainties, a low power research reactor Critical Facility was built in which cold clean fuel can be arranged in a desired and precise geometry. Different experiments conducted in this facility greatly contribute to understand and validate the physics design parameters

  10. Operating The Central Process Systems At Glenn Research Center

    Science.gov (United States)

    Weiler, Carly P.

    2004-01-01

    As a research facility, the Glenn Research Center (GRC) trusts and expects all the systems, controlling their facilities to run properly and efficiently in order for their research and operations to occur proficiently and on time. While there are many systems necessary for the operations at GRC, one of those most vital systems is the Central Process Systems (CPS). The CPS controls operations used by GRC's wind tunnels, propulsion systems lab, engine components research lab, and compressor, turbine and combustor test cells. Used widely throughout the lab, it operates equipment such as exhausters, chillers, cooling towers, compressors, dehydrators, and other such equipment. Through parameters such as pressure, temperature, speed, flow, etc., it performs its primary operations on the major systems of Electrical Dispatch (ED), Central Air Dispatch (CAD), Central Air Equipment Building (CAEB), and Engine Research Building (ERB). In order for the CPS to continue its operations at Glenn, a new contract must be awarded. Consequently, one of my primary responsibilities was assisting the Source Evaluation Board (SEB) with the process of awarding the recertification contract of the CPS. The job of the SEB was to evaluate the proposals of the contract bidders and then to present their findings to the Source Selecting Official (SSO). Before the evaluations began, the Center Director established the level of the competition. For this contract, the competition was limited to those companies classified as a small, disadvantaged business. After an industry briefing that explained to qualified companies the CPS and type of work required, each of the interested companies then submitted proposals addressing three components: Mission Suitability, Cost, and Past Performance. These proposals were based off the Statement of Work (SOW) written by the SEB. After companies submitted their proposals, the SEB reviewed all three components and then presented their results to the SSO. While the

  11. A case study of the remediation of Syncrude's Research Centre and the changes made in Syncrude's research operations

    International Nuclear Information System (INIS)

    Mueller, P.; Evans, P.; Ziervogel, H.; Parraguez, C.

    1996-01-01

    The new Research Centre for Syncrude Canada has made safeguarding the environment a priority. The former research facility in northeast Edmonton was decommissioned because of contamination at the site caused by more than 25 years of industrial operations. The process to decommission the site was based on a cost effective, phased approach to site dismantling, investigations and remediation. During the site remediation, several areas of contamination were found, with little background information to understand how the material had entered the soil. At he new facility a conscientious effort will be made to document all activities to prevent future occurrences of this type. 1 ref., 1 tab., 4 figs

  12. Collection and analysis of Health Physics Research Reactor operational and use data

    International Nuclear Information System (INIS)

    Sims, C.S.

    1985-04-01

    The Health Physics Research Reactor (HPRR) is the primary research tool at the Dosimetry Applications Research (DOSAR) Facility. In addition to use by the DOSAR staff, the HPRR is used by a wide segment of the scientific community for a variety of experimental purposes. This report is a compilation and analysis of data concerning HPRR uses, users, and operations through the end of FY 1984. 17 refs., 12 tabs.,

  13. 75 FR 27368 - Aerotest Operations, Inc., Aerotest Radiography and Research Reactor; Notice of Consideration of...

    Science.gov (United States)

    2010-05-14

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-228, NRC-2010-0178] Aerotest Operations, Inc., Aerotest Radiography and Research Reactor; Notice of Consideration of Approval of Transfer and Conforming... approving the indirect transfer of Facility Operating License No. R-98 for the Aerotest Radiography and...

  14. Psychometric model for safety culture assessment in nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

    2017-04-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  15. Psychometric model for safety culture assessment in nuclear research facilities

    International Nuclear Information System (INIS)

    Nascimento, C.S. do; Andrade, D.A.; Mesquita, R.N. de

    2017-01-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  16. Decommissioning and dismantling of nuclear research facilities in Switzerland: lessons learned

    International Nuclear Information System (INIS)

    Leibundgut, Fritz

    2017-01-01

    Paul Scherrer Institute is the largest research institute for natural and engineering science in Switzerland. It operated various nuclear facilities from 1960 to 2011: Research reactors DIORIT, SAPHIR and PROTEUS, and an incineration plant for low and medium level radioactive waste. Concerning SAPHIR research reactor: in operation from 1958 to 1993, planning of decommissioning from 1998 to 2000. Decommissioning work started in 2004. Finishing is planned for 2019. Concerning DIORIT research reactor: operation as DIORIT I (20 MWth) from 1960 to 1967, then reconstruction to DIORIT II (30 MWth) and operation from 1970 until 1977. Planning of decommissioning from 1992 to 1994. Decommissioning work started in 1994 and was finished in 2012. Concerning PROTEUS research reactor: in operation from 1966 to 2011. Planning of decommissioning from 2013 to 2014. Starting of decommissioning work is planned for 2017, finishing is planned for the end of 2018 Incineration plant: In operation from 1974 to 2002. Planning of decommissioning from 2011 to 2012. Starting of decommissioning work in 2016. Finishing planned for end of 2019. Treatment of various material categories from dismantling: Concerning aluminum: because of the production of H_2 during solidification in concrete, it was necessary to minimize the surface area. When dismantling research reactors, the aluminum removed was melted in an induction furnace and poured into a 4.5 m"3 concrete container to solidify. Cutting the metal and handling it was largely accomplished remote control, using conventional technology. Concerning Steel/Cast-iron: the storage containers to be filled determined the method used for reducing the size of these materials, and the technique used for handling them. The goal was to optimize the packing density to reduce repository costs. The selected method of reducing the size of components is to cut them up using diamond-tipped tools, like saw blades. Concerning Graphite: for graphite, grinding was the

  17. H-1NF: Australian national fusion plasma research facility

    International Nuclear Information System (INIS)

    Blackwell, B.D.; Borg, G.G.; Dewar, R.L.; Howard, J.; Gardner, H.J.; Rudakov, D.L.; Sharp, L.E.; Shats, M.G.; Warr, G.B.

    1997-01-01

    The H-1 heliac is a helical axis stellarator of moderate size and novel, flexible configuration. Since commissioning, H-1 has operated in quasi-continuous mode at low magnetic field. For higher fields ≤1T an ECRH heating system (28GHz, 200kW) has been installed under a collaborative agreement between ANU and NIFS. H-1 has recently been promoted to national facility status (H-1NF), which will include upgrades of the rf and ech heating systems to megawatt powers, and power supply and diagnostic and data system enhancements. This facilitates collaborative research locally (through the Australian Fusion Research Group consortium) and internationally. Results of a number of basic experiments in quasi-continuous mode are presented. (author)

  18. Operating experience feedback from safety significant events at research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Shokr, A.M. [Atomic Energy Authority, Abouzabal (Egypt). Egypt Second Research Reactor; Rao, D. [Bhabha Atomic Research Centre, Mumbai (India)

    2015-05-15

    Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

  19. Operating experience feedback from safety significant events at research reactors

    International Nuclear Information System (INIS)

    Shokr, A.M.

    2015-01-01

    Operating experience feedback is an effective mechanism to provide lessons learned from the events and the associated corrective actions to prevent recurrence of events, resulting in improving safety in the nuclear installations. This paper analyzes the events of safety significance that have been occurred at research reactors and discusses the root causes and lessons learned from these events. Insights from literature on events at research reactors and feedback from events at nuclear power plants that are relevant to research reactors are also presented along with discussions. The results of the analysis showed the importance of communication of safety information and exchange of operating experience are vital to prevent reoccurrences of events. The analysis showed also the need for continued attention to human factors and training of operating personnel, and the need for establishing systematic ageing management programmes of reactor facilities, and programmes for safety management of handling of nuclear fuel, core components, and experimental devices.

  20. Research in artificial intelligence for nuclear facilities

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1990-01-01

    The application of artificial intelligence, in the form of expert systems and neural networks, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, artificial intelligence can increase efficiency and effectiveness in a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) and in research facility experiments. Recent work at the University of Tennessee has demonstrated the feasibility of using neural networks to identify six different transients introduced into the simulation of a steam generator of a nuclear power plant. This work is now being extended to utilize data from a nuclear power plant training simulator. In one configuration, the inputs to the neural network are a subset of the quantities that are typical of those available from the safety parameter display system. The outputs of the network represent the various states of the plant (e.g., normal operation, coolant leakage, inadequate core flow, excessive peak fuel temperature, etc.). Training of the neural network is performed by introducing various faults or conditions to be diagnosed into the simulator. The goal of this work is to demonstrate a neural network diagnostic system that could provide advice to the operators in accordance with the emergency operating procedures

  1. Report on the operation of nuclear facilities in Slovenia in 1993

    International Nuclear Information System (INIS)

    Lovincic, D.

    1994-01-01

    The Slovenian Nuclear Safety Administration (SNSA) prepared a Report on Nuclear Safety in 1993 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into five thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia, the Posavje - 93 exercise and the operation of nuclear facilities around the world. (author)

  2. Report on the operation of nuclear facilities in Slovenia in 1993

    Energy Technology Data Exchange (ETDEWEB)

    Lovincic, D [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

    1994-07-01

    The Slovenian Nuclear Safety Administration (SNSA) prepared a Report on Nuclear Safety in 1993 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into five thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia, the Posavje - 93 exercise and the operation of nuclear facilities around the world. (author)

  3. An operator training simulator based on interactive virtual teleoperation: nuclear facilities maintenance applications

    International Nuclear Information System (INIS)

    Kim, Ki Ho; Kim, Seung Ho

    1997-01-01

    Remote manipulation in nuclear hazardous environment is very often complex and difficult to operate and requires excessively careful preparation. Remote slave manipulators for unstructured work are manually controlled by a human operator. Small errors made by the operator via the master manipulator during operation can cause the slave to be surffered from excessive forces and result in considerable damages to the slave iteself and its environment. In this paper, we present a prototype of an operator training simulator for use in nuclear facilities maintenance applications, as part of the ongoing Nuclear Robotics Development Program at Korea Atomic Energy Research Institute (KAERI). The operator training simulator provides a means by which, in virtual task simulation, the operator can try out and train for expected remote tasks that the real slave manipulator will perform in advance. The operator interacts with both the virtual slave and task environment through the real master. Virtual interaction force feedback is provided to the operator. We also describe a man-in-the loop control scheme to realize bilateral force reflection in virtual teleoperation

  4. Research studies performed using the Cairo Fourier Diffractometer Facility

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; Ridikas, D.

    2009-12-01

    This report represents the results of the research studies performed using the Cairo Fourier Diffractometer Facility (CFDF), within 10 years after it was installed and put into operation at the beginning of 1996. The main components of the CFDF were supplied by the IAEA according to the technical assistance project EGY/1/022 'Upgrading of Research Reactor Utilization'. The present report is the second published INDC report, while the first one, published at the beginning of 1997, was about the performance of the CFDF and its main characteristic parameters. Plenty of measurements were performed since then, yielding several publications both in local and international scientific periodicals and resulting in 8 M.Sc. and Ph.D. degrees from Egyptian Universities. In addition, a new approach for the analysis of the neutron spectra was implemented using the CFDF. Specially designed interface card with proper software program was applied instead of the reverse time of flight (RTOF) and Finnish made analyzer originally attached to the facility. It has been verified that the new approach can successfully replace the RTOF analyzer, significantly decreasing the time of measurement and saving the reactor's operation time. Besides, a special fault diagnostic system program was developed and tested for caring and handling the possible failures of the CFDF. Moreover, measurements were carried out for the diffraction spectra emitted at different points of one of the samples. The latter was scanned across the neutron beam of the CFDF, for studying the stress after welding; used in industrial applications. (author)

  5. An outline of research facilities of high intensity proton accelerator

    International Nuclear Information System (INIS)

    Tanaka, Shun-ichi

    1995-01-01

    A plan called PROTON ENGINEERING CENTER has been proposed in JAERI. The center is a complex composed of research facilities and a beam shape and storage ring based on a proton linac with an energy of 1.5 GeV and an average current of 10 mA. The research facilities planned are OMEGA·Nuclear Energy Development Facility, Neutron Facility for Material Irradiation, Nuclear Data Experiment Facility, Neutron Factory, Meson Factory, spallation Radioisotope Beam Facility, and Medium Energy Experiment Facility, where high intensity proton beam and secondary particle beams such as neutrons, π-mesons, muons, and unstable isotopes originated from the protons are available for promoting the innovative research of nuclear energy and basic science and technology. (author)

  6. The Pajarito Site operating procedures for the Los Alamos Critical Experiments Facility

    International Nuclear Information System (INIS)

    Malenfant, R.E.

    1991-12-01

    Operating procedures consistent with DOE Order 5480.6, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Los Alamos Critical Experiments Facility (LACEF) of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1983 and apply to any criticality experiment performed at the facility. 11 refs

  7. Operation of the Brookhaven National Laboratory Accelerator Test Facility

    International Nuclear Information System (INIS)

    Batchelor, K.; Ben-Zvi, I.; Botke, I.; Chou, T.S.; Fernow, R.; Fischer, J.; Fisher, A.; Gallardo, J.; Ingold, G.; Malone, R.; Palmer, R.; Parsa, Z.; Pogorelsky, I.; Rogers, J.; Sheehan, J.; Srinivasan-Rao, T.; Tsang, T.; Ulc, S.; van Steenbergen, A.; Wang, X.J.; Woodle, M.; Yu, L.H.

    1992-01-01

    Early operation of the 50 MeV high brightness electron linac of the Accelerator Test Facility is described along with experimental data. This facility is designed to study new linear acceleration techniques and new radiation sources based on linacs in combination with free electron lasers. The accelerator utilizes a photo-excited, metal cathode, radio frequency electron gun followed by two travelling wave accelerating sections and an Experimental Hall for the study program

  8. Operators guide: Atmospheric Release Advisory Capability (ARAC) site facility

    International Nuclear Information System (INIS)

    Cassaro, E.; Lomonaco, L.

    1979-01-01

    The Atmospheric Release Advisory Capability (ARAC) is designed to help officials at designated DOE sites and other locations in estimating the effects of atmospheric releases of radionuclides or other hazardous materials by issuing real-time advisories to guide them in their planning. This report outlines the capabilities and sources of ARAC, and in more detail describes an ARAC Site Facility, its operating procedures and interactions with the ARAC Central Facility (ACF) located at LLL

  9. NIST Accelerator Facilities And Programs In Support Of Industrial Radiation Research

    International Nuclear Information System (INIS)

    Bateman, F.B.; Desrosiers, M.F.; Hudson, L.T.; Coursey, B.M.; Bergstrom, P.M. Jr.; Seltzer, S.M.

    2003-01-01

    NIST's Ionizing Radiation Division maintains and operates three electron accelerators used in a number of applications including waste treatment and sterilization, radiation hardness testing, detector calibrations and materials modification studies. These facilities serve a large number of governmental, academic and industrial users as well as an active intramural research program. They include a 500 kV cascaded-rectifier accelerator, a 2.5 MV electron Van de Graaff accelerator and a 7 to 32 MeV electron linac, supplying beams ranging in energy from a few keV up to 32 MeV. In response to the recent anthrax incident, NIST along with the US Postal Service and the Armed Forces Radiobiology Research Institute (AFRRI) are working to develop protocols and testing procedures for the USPS mail sanitization program. NIST facilities and personnel are being employed in a series of quality-assurance measurements for both electron- and photon-beam sanitization. These include computational modeling, dose verification and VOC (volatile organic compounds) testing using megavoltage electron and photon sources

  10. A durability analysis of the Cascad facility based on feedback obtained after 10 years of operation

    International Nuclear Information System (INIS)

    Samoel, R.; Canas, D.; Henry, H.; Battesti, P.

    1999-01-01

    The CASCAD facility at the nuclear research centre in Cadarache is a dry storage facility for spent fuel that has been placed in a vault. Feedback on its design and performance after 10 years of operation was obtained in order to identify the factors limiting its life time. This assessment corresponds to a durability analysis based on a combination of dependability methods. This is a critical analysis identifying the risks involving failure of the components when they are subjected to internal and external disturbances (aging, technology obsolescence, etc.). The measures to be implemented to extend the life time of the facility are subsequently enumerated. A proposed synthesis or 'logic diagram' of the analysis is also presented. (authors)

  11. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  12. Research activities by INS cyclotron facility

    International Nuclear Information System (INIS)

    1992-06-01

    Research activities made by the cyclotron facility and the related apparatuses at Institute for Nuclear Study (INS), University of Tokyo, have been reviewed in terms of the associated scientific publications. This publication list, which is to be read as a continuation of INS-Rep.-608 (October, 1986), includes experimental works on low-energy nuclear physics, accelerator technology, instrumental developments, radiation physics and other applications in interdisciplinary fields. The publications are classified into the following four categories. (A) : Internal reports published in INS. (B) : Publications in international scientific journals on experimental research works done by the cyclotron facility and the related apparatuses at INS. Those made by outside users are also included. (C) : Publications in international scientific journals on experimental low-energy nuclear physics, which have been done by the staff of INS Nuclear Physics Division using facilities outside INS. (D) : Contributions to international conferences. (author)

  13. Progress towards a new Canadian irradiation-research facility

    International Nuclear Information System (INIS)

    Lee, A.G.; Lidstone, R.F.

    1993-01-01

    As reported at the second meeting of the International Group on Research Reactors, Atomic Energy of Canada Limited (AECL) is evaluating its options for future irradiation facilities. During the past year significant progress has been made towards achieving consensus on the irradiation requirements for AECL's major research programs and interpreting those requirements in terms of desirable characteristics for experimental facilities in a research reactor. The next stage of the study involves identifying near-term and long-term options for irradiation-research facilities to meet the requirements. The near-term options include assessing the availability of the NRU reactor and the capabilities of existing research reactors. The long-term options include developing a new irradiation-research facility by adapting the technology base for the MAPLE-X10 reactor design. Because materials testing in support of CANDU power reactors dominates AECL's irradiation requirements, the new reactor concept is called the MAPLE Materials Testing Reactor (MAPLE-MTR). Parametric physics and engineering studies are in progress on alternative MAPLE-MTR configurations to assess the capabilities for the following types of test facilities: - fast-neutron sites, that accommodate materials-irradiation assemblies, - small-diameter vertical fuel test loops that accommodate multielement assemblies, - large-diameter vertical fuel test loops, each able to hold one or more CANDU fuel bundles, - horizontal test loops, each able to hold full-size CANDU fuel bundles or small-diameter multi-element assemblies, and - horizontal beam tubes

  14. Decommissioning of nuclear facilities involving operations with uranium and thorium

    International Nuclear Information System (INIS)

    Shum, E.Y.; Neuder, S.M.

    1990-01-01

    When a licensed nuclear facility ceases operation, the U.S. Nuclear Regulatory Commission (NRC) ensures that the facility and its site are decontaminated to acceptable levels so they may safely be released for unrestricted public use. Because specific environmental standards or broad federal guidelines governing release of residual radioactive contamination have not been issued, NRC has developed ad hoc cleanup criteria for decommissioning nuclear facilities that involved uranium and thorium. Cleanup criteria include decontamination of buildings, equipment, and land. We will address cleanup criteria and their rationale; procedures for decommissioning uranium/thorium facilities; radiological survey designs and procedures; radiological monitoring and measurement; and cost-effectiveness to demonstrate compliance

  15. Operability test procedure for PFP wastewater sampling facility

    International Nuclear Information System (INIS)

    Hirzel, D.R.

    1995-01-01

    Document provides instructions for performing the Operability Test of the 225-WC Wastewater Sampling Station which monitors the discharge to the Treated Effluent Disposal Facility from the Plutonium Finishing Plant. This Operability Test Procedure (OTP) has been prepared to verify correct configuration and performance of the PFP Wastewater sampling system installed in Building 225-WC located outside the perimeter fence southeast of the Plutonium Finishing Plant (PFP). The objective of this test is to ensure the equipment in the sampling facility operates in a safe and reliable manner. The sampler consists of two Manning Model S-5000 units which are rate controlled by the Milltronics Ultrasonic flowmeter at manhole No.C4 and from a pH measuring system with the sensor in the stream adjacent to the sample point. The intent of the dual sampling system is to utilize one unit to sample continuously at a rate proportional to the wastewater flow rate so that the aggregate tests are related to the overall flow and thereby eliminate isolated analyses. The second unit will only operate during a high or low pH excursion of the stream (hence the need for a pH control). The major items in this OTP include testing of the Manning Sampler System and associated equipment including the pH measuring and control system, the conductivity monitor, and the flow meter

  16. The radiological research accelerator facility: Progress report for the period December 1, 1986-November 30, 1987

    International Nuclear Information System (INIS)

    1987-04-01

    Experiments performed at the Radiological Research Accelerator Facility (RARAF) during the period of July 1986 through April 1987 are listed, as well as experiments run prior to that period and expected to eventually resume. The experiments run since July 1, 1986 or expected to run before November 30, 1987 are briefly described. Accelerator use and operation is summarized, as well as facilities development and activities of the Scientific Advisory Committee

  17. Safety evaluation of the NSRR facility relevant to the modification for improved pulse operation and preirradiated fuel experiments

    International Nuclear Information System (INIS)

    Inabe, Teruo; Terakado, Yoshibumi; Tanzawa, Sadamitsu; Katagiri, Hiroshi; Kobayashi, Hideo

    1988-11-01

    The Nuclear Safety Research Reactor (NSRR) is a pulse reactor for the inpile experiments to study the fuel behavior under reactivity initiated accident conditions. The present operation modes of the NSRR consist of the steady state operation up to 300 kW and the natural pulse operation in which a sharp pulsed power is generated from substantially zero power level. In addition to these, two new modes of shaped pulse operation and combined pulse operation will be conducted in the near future as the improved pulse operations. A transient power up to 10 MW will be generated in the shaped pulse operation, and a combination of a transient power up to 10 MW and a sharp pulsed power will be generated in the combined pulse operation. Furthermore, preirradiated fuel rods will be employed in the future experiments whereas the present experiments are confined to the test specimens of unirradiated fuel rods. To provide for these programs, the fundamental design works relevant to the modification of the reactor facility including the reactor instrumentation and control systems and experimental provision were developed. The reactor safety evaluation is prerequisite for confirming the propriety of the fundamental design of the reactor facility from the safety point of view. The safety evaluation was therefore conducted postulating such events that would bring about abnormal conditions in the reactor facility. As a result of the safety evaluation, it has been confirmed as to the NSRR facility after modification that the anticipated transients, the postulated accidents, the major accident and the hypothetical accident do not result respectively in any serious safety problem and that the fundamental design principles and the reactor siting are adequate and acceptable. (author)

  18. The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)

    International Nuclear Information System (INIS)

    1994-12-01

    The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration

  19. Operation of the Brookhaven national laboratory accelerator test facility

    International Nuclear Information System (INIS)

    Batchelor, K.; Ben-Zvi, I.; Botke, I.; Chou, T.S.; Fernow, R.; Fischer, J.; Fisher, A.; Gallardo, J.; Ingold, G.; Malone, R.; Palmer, R.; Parsa, Z.; Pogorelsky, I.; Rogers, J.; Sheehan, J.; Srinivasan-Rao, T.; Tsang, T.; Ulc, S.; Van Steenbergen, A.; Wang, X.J.; Woodle, M.; Yu, L.H.

    1992-01-01

    Early operation of the 50 MeV high brightness electron linac of the Accelerator Test Facility is described along with experimental data. This facility is designed to study new linear acceleration techniques and new radiation sources based on linacs in combination with free electron lasers. The accelerator utilizes a photo-excited, metal cathode, radio frequency electron gun followed by two travelling wave accelerating sections and an Experimental Hall for the study program. (Author) 5 refs., 4 figs., tab

  20. Evaluation of physical facilities and processing operations of major ...

    African Journals Online (AJOL)

    ADEYEYE

    abattoirs were as a result of failure to enforce the use of standard facilities in carrying out abattoir operations and general maintenance ... incinerator, chemical treatment and disposal. Sub- .... Veterinary laboratory .... sustainable food security.

  1. Ten years of cryo-magnetic W7-X test facility construction and operation

    International Nuclear Information System (INIS)

    Renard, B.; Dispau, G.; Donati, A.; Genini, L.; Gournay, J.F.; Kuster, O.; Molinie, F.; Schild, T.; Touzery, R.; Vieillard, L.; Walter, C.

    2011-01-01

    The construction, commissioning, and operation phases of the W7-X cryo-magnetic test facility in CEA Saclay lasted ten years. The large diversity of equipments called, specialties involved and problems solved attest the expertise that was required to operate the test facility and test the coils. Nearly one hundred cryogenic tests were performed on the seventy W7-X coils, at a rate always increasing, using two cryostats each holding two coils. This paper presents the test facility and its operation first, the cryogenic difficulties that were confronted with their solutions, the electro-magnetic difficulties encountered along with corrective actions, and finally the instrumentation and data acquisition aspects. (authors)

  2. Research on common methods for evaluating the operation effect of integrated wastewater treatment facilities of iron and steel enterprises

    Science.gov (United States)

    Bingsheng, Xu

    2017-04-01

    Considering the large quantities of wastewater generated from iron and steel enterprises in China, this paper is aimed to research the common methods applied for evaluating the integrated wastewater treatment effect of iron and steel enterprises. Based on survey results on environmental protection performance, technological economy, resource & energy consumption, services and management, an indicator system for evaluating the operation effect of integrated wastewater treatment facilities is set up. By discussing the standards and industrial policies in and out of China, 27 key secondary indicators are further defined on the basis of investigation on main equipment and key processes for wastewater treatment, so as to determine the method for setting key quantitative and qualitative indicators for evaluation indicator system. It is also expected to satisfy the basic requirements of reasonable resource allocation, environmental protection and sustainable economic development, further improve the integrated wastewater treatment effect of iron and steel enterprises, and reduce the emission of hazardous substances and environmental impact.

  3. Low-level tritium research facility for the University of Toronto Institute for Aerospace Studies

    International Nuclear Information System (INIS)

    Kherani, N.P.; Shmayda, W.T.

    1984-06-01

    The objective of the Low-level Tritium Research Facility for the University of Toronto Institute for Aerospace Studies (UTIAS) is to investigate tritium-material interactions and how they differ with respect to protium and deuterium. The tritium laboratory will also be employed to study tritium retention, tritium imaging, and the effect of tritium on diagnostic devices. This report is a preliminary design document of the UTIAS Low-Level Tritium Research Facility including the fundamentals of tritium, a description of the facility, tritium laboratory requirements and the safety analysis of the laboratory. The facility is designed to handle a total elemental tritium inventory of 10 Ci, though it will initially commence operation with 1 Ci and later increased to the maximum value. In the event of an instantaneous emission of the total tritium inventory within the laboratory, the working personnel would be exposed to an airborne tritium concentration less than the maximum permissible. Moreover, with all the safety features included in this design the likelihood of such an accident is very remote. Thus, the tritium laboratory design is intrinsically safe

  4. Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

  5. Safety training and safe operating procedures written for PBFA [Particle Beam Fusion Accelerator] II and applicable to other pulsed power facilities

    International Nuclear Information System (INIS)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards

  6. Low-level wastewater treatment facility process control operational test report

    International Nuclear Information System (INIS)

    Bergquist, G.G.

    1996-01-01

    This test report documents the results obtained while conducting operational testing of a new TK 102 level controller and total outflow integrator added to the NHCON software that controls the Low-Level Wastewater Treatment Facility (LLWTF). The test was performed with WHC-SD-CP-OTP 154, PFP Low-Level Wastewater Treatment Facility Process Control Operational Test. A complete test copy is included in appendix A. The new TK 102 level controller provides a signal, hereafter referred to its cascade mode, to the treatment train flow controller which enables the water treatment process to run for long periods without continuous operator monitoring. The test successfully demonstrated the functionality of the new controller under standard and abnormal conditions expected from the LLWTF operation. In addition, a flow totalizer is now displayed on the LLWTF outlet MICON screen which tallies the process output in gallons. This feature substantially improves the ability to retrieve daily process volumes for maintaining accurate material balances

  7. KSC facilities status and planned management operations. [for Shuttle launches

    Science.gov (United States)

    Gray, R. H.; Omalley, T. J.

    1979-01-01

    A status report is presented on facilities and planned operations at the Kennedy Space Center with reference to Space Shuttle launch activities. The facilities are essentially complete, with all new construction and modifications to existing buildings almost finished. Some activity is still in progress at Pad A and on the Mobile Launcher due to changes in requirements but is not expected to affect the launch schedule. The installation and testing of the ground checkout equipment that will be used to test the flight hardware is now in operation. The Launch Processing System is currently supporting the development of the applications software that will perform the testing of this flight hardware.

  8. Radiological safety experience in nuclear fuel cycle operations at Bhabha Atomic Research Center, Trombay, Mumbai, India

    International Nuclear Information System (INIS)

    Pushparaja; Gopalakrishnan, R.K.; Subramaniam, G.

    2000-01-01

    Activities at Bhabha Atomic Research Centre (BARC), Mumbai, cover nuclear fuel cycle operations based on natural uranium as the fuel. The facilities include: plant for purification and production of nuclear grade uranium metal, fuel fabrication, research reactor operation, fuel reprocessing and radioactive waste management in each stage. Comprehensive radiation protection programmes for assessment and monitoring of radiological impact of these operations, both in occupational and public environment, have been operating in BARC since beginning. These programmes, based on the 1990 ICRP Recommendations as prescribed by national regulatory body, the Atomic Energy Regulatory Board (AERB), are being successfully implemented by the Health, Safety and Environment Group, BARC. Radiation Hazards Control Units attached to the nuclear fuel cycle facilities provide radiation safety surveillance to the various operations. The radiation monitoring programme consists of measurement and control of external exposures by thermoluminescent dosimeters (TLDs), hand-held and installed instruments, and internal exposures by bioassay and direct whole body counting using shadow shield counter for beta gamma emitters and phoswich detector based system for plutonium. In addition, an environmental monitoring programme is in place to assess public exposures resulting from the operation of these facilities. The programme involves analysis of various matrices in the environment such as bay water, salt, fish, sediment and computation of resulting public exposures. Based on the operating experience in these plants, improved educating and training programmes for plant operators, have been designed. This, together with the application of new technologies have brought down individual as well as average doses of occupational workers. The environmental releases remain a small fraction of the authorised limits. The operating health physics experience in some of these facilities is discussed in this paper

  9. Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

    OpenAIRE

    M. V. Vedernikova; I. A. Pron; M. N. Savkin; N. S. Cebakovskaya

    2017-01-01

    This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on d...

  10. The experimental sodium facility NAVA

    International Nuclear Information System (INIS)

    Langenbrunner, H.; Grunwald, G.; May, R.

    1976-01-01

    Within the framework of preparations for the introduction of sodium cooled fast breeder reactors an experimental sodium facility was installed at the Central Institute of Nuclear Research at Rossendorf. Design, engineering aspects and operation of this facility are described; operating experience is briefly discussed. (author)

  11. Operations aspects of the Fermilab Central Helium Liquefier facility

    International Nuclear Information System (INIS)

    Geynisman, M.G.; Makara, J.N.

    1996-09-01

    The Fermilab Central Helium Liquefier (CHL) facility consists of helium and nitrogen reliquefier plants operated 24 hours-a-day to supply LHe at 4.6 K and LN 2 for the Fermilab Tevatron superconducting proton-antiproton collider ring and to recover warm return gases. Operating aspects of CHL, including different equipment and systems reliability, availability, maintenance experience, safety concerns, and economics aspects are discussed

  12. Operations aspects of the Fermilab Central Helium Liquefier Facility

    International Nuclear Information System (INIS)

    Geynisman, M.G.; Makara, J.N.

    1995-03-01

    The Fermilab Central Helium Liquefier (CHL) facility consists of helium and nitrogen reliquefier plants operated 24 hours-a-day to supply LHe at 4.6 degrees K and LN 2 for the Fermilab Tevatron superconducting proton-antiproton collider ring and to recover warm return gases. Operating aspects of CHL, including different equipment and systems reliability, availability, maintenance experience, safety concerns, and economics aspects are discussed

  13. Preliminary analysis of the operating characteristics of a generic repository receiving facility: Status report

    International Nuclear Information System (INIS)

    1985-10-01

    The operating characteristics of a repository receiving facility structured around current technology and practices have been reviewed. Cask turnaround times and operator doses were estimated. Large throughout and long-term receiving operations at a nuclear waste repository result in an unprecedented number of casks being handled. While the current generation of material-handling equipment is adequate to process the casks, personnel radiation exposures for the generic facility analyzed are unacceptably high. This emphasizes the need for development of occupational radiation exposure control concepts for application in repository receiving facilities. 3 refs., 22 figs., 6 tabs

  14. A low-temperature research facility for space

    International Nuclear Information System (INIS)

    Donnelly, R.J.

    1991-01-01

    The Jet Propulsion Laboratory is proposing to NASA a new initiative to construct a Low Temperature Research Facility for use in space. The facility is described, together with some details of timing and support. An advisory group has been formed which seeks to advise JPL and NASA of the capabilities required in this facility and to invite investigators to propose experiments which require the combination of low temperature and reduced gravity to be successful. (orig.)

  15. Start of operation of the barrel measuring facility II-01. Implementation into operational processes

    International Nuclear Information System (INIS)

    Buesing, B.; Escher, M.

    2013-01-01

    For the operation of the barrel measuring facility (FAME) II-01 a variety requirements to the measuring techniques were defined and tested in the frame of start-up. The used mechanical engineering and measuring technique complies with the state-of-the-art. Using the barrel measuring facility quality assured determinations of the dose rate and the nuclide-specific activity inventory were performed. For the evaluation of the gamma spectrometric measurements of FAME II-01 appropriately qualified personnel is available. The implementation of the facility in combination with the connection to the data base system PIK-AS and AVK it guaranteed that important data are available in real-time for the measuring process and the subsequent work steps. Besides this it is guaranteed that using the import/export functions relevant data are reviewed, supplemented and exchanged between the systems without transfer errors. The determined data of the dose rate and gamma spectrometric measurements allow an activity determination of the waste package with quality assurance and close to reality. Conservative assumptions in the frame of activity calculations for the later final disposal can be reduced. The automated operation of FAME allows also the reduction of radiation exposure of the personnel.

  16. Space Infrared Telescope Facility (SIRTF) - Operations concept. [decreasing development and operations cost

    Science.gov (United States)

    Miller, Richard B.

    1992-01-01

    The development and operations costs of the Space IR Telescope Facility (SIRTF) are discussed in the light of minimizing total outlays and optimizing efficiency. The development phase cannot extend into the post-launch segment which is planned to only support system verification and calibration followed by operations with a 70-percent efficiency goal. The importance of reducing the ground-support staff is demonstrated, and the value of the highly sensitive observations to the general astronomical community is described. The Failure Protection Algorithm for the SIRTF is designed for the 5-yr lifetime and the continuous venting of cryogen, and a science driven ground/operations system is described. Attention is given to balancing cost and performance, prototyping during the development phase, incremental development, the utilization of standards, and the integration of ground system/operations with flight system integration and test.

  17. Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

  18. Decommissioning of medical, industrial and research facilities. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

  19. Comparative Study on Research Reactor Operation Requirements of IAEA and Korea

    International Nuclear Information System (INIS)

    Yune, Young Gill; Chang, Woo Joon; Lee, Jinho

    2014-01-01

    The IAEA safety requirements represent a consensus view of the IAEA's member states and encompass the recommendations of international experts for the safety of the research reactor. The IAEA safety standards are acknowledged as a global standard by most countries in the world. Therefore, it is desirable to harmonize domestic safety requirements with those of the IAEA. Also, since the IAEA safety requirements include international endeavors to strengthen nuclear safety and to apply the latest nuclear safety technologies to nuclear facilities, a comparative analysis of the safety requirements of the IAEA and Korea for the research reactor will be beneficial to obtaining the insights to improve regulations of the research reactor in Korea. For the reason, a comparative study has been conducted for the research reactor operation safety requirements of the IAEA and Korea in this paper. This paper briefly introduced operation safety requirements in the NS-R-4, analysis methods of this study, and the analysis results. A comparative study has been performed on research reactor operation safety requirements of the IAEA and Korea. This study has identified some gaps in operation safety requirements for the NPP of Korea, comparing with those for the research reactor of the IAEA in the following areas: periodic safety assessment, utilization and modification of the reactor, extended shutdown, inspection/testing/maintenance, operating organization, emergency planning, and commissioning

  20. French experience of regulation and operation on reprocessing facilities of LWR spent fuels

    Energy Technology Data Exchange (ETDEWEB)

    Mercier, J P [DES/SESUL (France)

    1992-02-01

    This presentation describes the French experience of regulation and operation on reprocessing facilities: how the safety assessment was made of UP3-A plant of the La Hague establishment for the building permit and operating license within the context of French nuclear regulations and the national debate on the need for reprocessing. Other factors discussed are how the public was involved, how the regulations were improved in the process and what the different stages of commissioning consisted of. In the design studies of a reprocessing facility, three complementary approaches are used: - observance of regulations born of technical considerations, and good practice, - analysis of the hazards, using deterministic and probabilistic methods, within the framework of a safety report, - review of experience feedback from such a facility or like plants. The design of the facility must permit the prevention of accidents and limit their consequences. Moreover, during all foreseeable cases (normal operating, incidents and accidents), the safety of the staff, the public and the environment with regard to consequences of radioactive releases and ionising radiations must be ensured. In the evaluation of these consequences, the approach used is voluntarily pessimistic in order to take into account every possible case. It is based on the main following principles: definition of the events considered for the dimensioning of the facility; redundancy and diversification; defense in depth which consists of the multiplication of the barriers. The experience feedback comes, on the one hand from operator's findings aiming at improving its facility, on the other hand from incidents, the lessons of which being taken into account after careful analysis. These incidents are analyzed by the Safety Authority upon presentation of the data by the operator and on site findings of inspections. In other respects, the aim of inspections is to check that the plant and its operating practices are

  1. Quality Assurance of ARM Program Climate Research Facility Data

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, RA; Kehoe, KE; Sonntag, KL; Bahrmann, CP; Richardson, SJ; Christensen, SW; McCord, RA; Doty, DJ; Wagener, Richard [BNL; Eagan, RC; Lijegren, JC; Orr, BW; Sisterson, DL; Halter, TD; Keck, NN; Long, CN; Macduff, MC; Mather, JH; Perez, RC; Voyles, JW; Ivey, MD; Moore, ST; Nitschke, DL; Perkins, BD; Turner, DD

    2008-03-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and haracterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented.

  2. Quality Assurance of ARM Program Climate Research Facility Data

    International Nuclear Information System (INIS)

    Peppler, R.A.; Kehoe, K.E.; Sonntag, K.L.; Bahramann, C.P.; Richardson, S.J.; Christensen, S.W.; McCord, R.A.; Doty, D.J.; Wagener, R.; Eagan, R.C.; Lijegren, J.C.; Orr, B.W.; Sisterson, D.L.; Halter, T.D.; Keck, N.N.; Long, C.N.; Macduff, M.C.; Mather, J.H.; Perez, R.C.; Voyles, J.W.; Ivey, M.D.; Moore, S.T.; Nitschke, D.L.; Perkins, B.D.; Turner, D.D.

    2008-01-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and characterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented

  3. CLEAR test facility

    CERN Multimedia

    Ordan, Julien Marius

    2017-01-01

    A new user facility for accelerator R&D, the CERN Linear Electron Accelerator for Research (CLEAR), started operation in August 2017. CLEAR evolved from the former CLIC Test Facility 3 (CTF3) used by the Compact Linear Collider (CLIC). The new facility is able to host and test a broad range of ideas in the accelerator field.

  4. Operational safety analysis of the Olkiluoto encapsulation plant and disposal facility; Olkiluodon kapselointi- ja loppusijoituslaitoksen kaeyttoeturvallisuusanalyysi

    Energy Technology Data Exchange (ETDEWEB)

    Rossi, J.; Suolanen, V. [VTT Technical Research Centre of Finland, Espoo (Finland)

    2012-11-15

    Radiation doses for workers of the facility, for inhabitants in the environment and for terrestrial ecosystem possibly caused by the encapsulation and disposal facilities to be built at Olkiluoto during its operation were considered in the study. The study covers both the normal operation of the plant and some hypothetical incidents and accidents. Release through the ventilation stack is assumed to be filtered both in normal operation and in hypothetical abnormal fault and accident cases. In addition the results for unfiltered releases are also presented. This research is limited to the deterministic analysis. During about 30 operation years of our four nuclear power plant units there have been found 58 broken fuel pins. Roughly estimating there has been one fuel leakage per year in a facility (includes two units). Based on this and adopting a conservative approach, it is estimated that one fuel pin per year could leak in normal operation during encapsulation process. The release magnitude in incidents and accidents is based on the event chains, which lead to loss of fuel pin tightness followed by a discharge of radionuclides into the handling space and to some degree to the atmosphere through the ventilation stack equipped with redundant filters. The most exposed group of inhabitants is conservatively assumed to live at the distance of 200 meters from the encapsulation and disposal plant and it will receive the largest doses in most dispersion conditions. The dose value to a member of the most exposed group was calculated on the basis of the weather data in such a way that greater dose than obtained here is caused only in 0.5 percent of dispersion conditions. The results obtained indicate that during normal operation the doses to workers remain small and the dose to the member of the most exposed group is less than 0.001 mSv per year. In the case of hypothetical fault and accident releases the offsite doses do not exceed either the limit values set by the safety

  5. Space Station life science research facility - The vivarium/laboratory

    Science.gov (United States)

    Hilchey, J. D.; Arno, R. D.

    1985-01-01

    Research opportunities possible with the Space Station are discussed. The objective of the research program will be study gravity relationships for animal and plant species. The equipment necessary for space experiments including vivarium facilities are described. The cost of the development of research facilities such as the vivarium/laboratory and a bioresearch centrifuge is examined.

  6. Collective statement on major nuclear safety research facilities and programmes at risk

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear safety research remains necessary, since nuclear power programmes are dynamic. In addition to maintaining in-depth competencies, its aim is to provide information to plant designers, operators and regulators in support of the resolution of safety issues, to strengthen confidence in their solution and their implementation, and also to anticipate problems of potential significance. New fields of research open up as a result of plant ageing, plant life extension, plant up-rating, optimisation of plant economics and the associated need to further reduce uncertainties in safety margins quantification. The safety evaluation of future reactor systems being developed or considered in several Member countries also requires new research efforts. Accordingly, Member countries are encouraged to support efforts to maintain key research data, facilities and programmes through national support of international co-operation and funding. This should be under-pinned by development of short-, medium- and long-term strategic visions of the needs of the nuclear safety research community, including a strong component of international collaboration given the international nature of nuclear safety issues. (author)

  7. Progress report concerning safety research for nuclear reactor facilities

    International Nuclear Information System (INIS)

    1978-01-01

    Examination and evaluation of safety research results for nuclear reactor facilities have been performed, as more than a year has elapsed since the plan had been initiated in April, 1976, by the special sub-committee for the safety of nuclear reactor facilities. The research is carried out by being divided roughly into 7 items, and seems to be steadily proceeding, though it does not yet reach the target. The above 7 items include researches for (1) criticality accident, (2) loss of coolant accident, (3) safety for light water reactor fuel, (4) construction safety for reactor facilities, (5) reduction of release of radioactive material, (6) safety evaluation based on the probability theory for reactor facilities, and (7) aseismatic measures for reactor facilities. With discussions on the progress and the results of the research this time, research on the behaviour on fuel in abnormal transients including in-core and out-core experiments has been added to the third item, deleting the power-cooling mismatch experiment in Nuclear Safety Research Reactor of JAERI. Also it has been decided to add two research to the seventh item, namely measured data collection, classification and analysis, and probability assessment of failures due to an earthquake. For these 7 items, the report describes the concrete contents of research to be performed in fiscal years of 1977 and 1978, by discussing on most rational and suitable contents conceivable at present. (Wakatsuki, Y.)

  8. The operating organization and the recruitment, training and qualification of personnel for research reactors. Safety guide

    International Nuclear Information System (INIS)

    2008-01-01

    This Safety Guide provides recommendations on meeting the requirements on the operating organization and on personnel for research reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization

  9. Operation of post-irradiation examination facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eun Ka; Park, Kwang Joon; Jeon, Yong Bum [and others; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    In 1995, the post-irradiation examination (PIE) of nuclear fuels was performed as follows. The relation between burnup and top nozzle spring force of fuel assembly was obtained by measuring the holddown spring force on the Kori-1 reactor fuel assemblies. The resonance ultrasonic test for inspection of defect and moisture in fuel rod was carried out on fuel rods of C15 and J14 assemblies, and the change of fuel rod condition by storing in pool has been analyzed on the intentionally defected fuel rods (ID-C and ID-L) as well as intact fuel rod (1-2) by NDT in ht cell. The oxide layer thickness on cladding surface of J44-L12 fuel rod was measured by NDT method and metallography to reveal the oxidation as a function of temperature in the fuel rod, and the burnup of J44 fuel assembly was measured by chemical analysis. HVAC system and pool water treatment system of the PIE facility were continuously operated for air filtration and water purification. The monitoring of radiation and pool water in PIE facility has been carried out to maintain the facility safety, and electric power supply system was checked and maintained to supply the electric power to the facility normally. The developed measurement techniques of oxide layer thickness on fuel rod cladding and holddown spring force of top nozzle in fuel assembly were applied to examine the nuclear fuels. Besides, a radiation shielding glove box was designed and a hot cell compressor for volume reduction of radioactive materials was fabricated. 19 tabs., 38 figs., 7 refs. (Author) .new.

  10. Operation and Maintenance of Water Pollution Control Facilities: A WPCF White Paper.

    Science.gov (United States)

    Hill, William R.; And Others

    1979-01-01

    Presented are the recommendations of the Water Pollution Control Federation for operation and maintenance consideration during the planning design, construction, and operation of wastewater treatment facilities. (CS)

  11. Networking strategies of the microscopy community for improved utilization of advanced instruments: (1) The Australian Microscopy and Microanalysis Research Facility (AMMRF)

    International Nuclear Information System (INIS)

    Ringer, S.P.; Apperley, M.H.

    2014-01-01

    This paper describes the strategy underpinning the formation and operation of the Australian Microscopy and Microanalysis Research Facility (AMMRF). AMMRF is a formal collaboration that links eight Australian Universities together to create a user-focused national capability in microscopy and microanalysis. The AMMRF flagship capabilities include: Cameca IMS-1280 and NanoSIMS-50 ion microprobes (University of Western Australia); High-throughput, high-resolution cryoTEM (University of Queensland); Atom Probe Microscopy (University of Sydney); High-resolution Focussed Ion-Beam and SEM (Universities of Adelaide and NSW); High-resolution SEM microanalysis facility (University of New South Wales); and PHI TRIFT V nanoToF ToF-SIMS (University of South Australia). Secondly, a network of peer support and expert training has been established amongst facility professional support staff. The governance and funding of the organisation are described and the advantages and achievements of a nationally coordinated facility for microscopy and microanalysis are set out. Selected data are presented that benchmark the performance of the facility, describe the economic impact and demonstrate the impact on the quality of research outcomes as a result of operating national collaborative research infrastructure for microscopy and microanalysis

  12. Impacts of ramping inflexibility of conventional generators on strategic operation of energy storage facilities

    DEFF Research Database (Denmark)

    Nasrolahpour, Ehsan; Kazempour, Jalal; Zareipour, Hamidreza

    2016-01-01

    This paper proposes an approach to assist a pricemaker merchant energy storage facility in making its optimal operation decisions. The facility operates in a pool-based electricity market, where the ramping capability of other resources is limited. Also, wind power resources exist in the system...

  13. Public Facilities Management and Action Research for Sustainability

    DEFF Research Database (Denmark)

    Galamba, Kirsten Ramskov

    Current work is the main product of a PhD study with the initial working title ‘Sustainable Facilities Management’ at Centre for Facilities Management – Realdania Research, DTU Management 1. December 2008 – 30. November 2011. Here the notion of Public Sustainable Facilities Management (FM......) is analysed in the light of a change process in a Danish Municipal Department of Public Property. Three years of Action Research has given a unique insight in the reality in a Municipal Department of Public Property, and as to how a facilitated change process can lead to a more holistic and sustainable...

  14. Fast Flux Test Facility sodium pump operating experience - mechanical

    International Nuclear Information System (INIS)

    Buonamici, R.

    1987-11-01

    The Heat Transport System (HTS) pumps were designed, fabricated, tested, and installed in the Fast Flux Test Facility (FFTF) Plant during the period from September 1970 through July 1977. Since completion of the installation and sodium fill in December 1978, the FFTF Plant pumps have undergone extensive testing and operation with HTS testing and reactor operation. Steady-state hydraulic and mechanical performances have been and are excellent. In all, FFTF primary and secondary pumps have operated in sodium for approximately 75,000 hours and 79,000 hours, respectively, to August 24, 1987

  15. Research on the application of PPP model in the Chinese construction and operation of new energy vehicle charging facilities

    Science.gov (United States)

    Zhu, Liping

    2017-05-01

    New energy car charging equipment is the development and popularization of new energy vehicles. It has the nature of quasi-public goods. Due to the large number of construction projects, wide distribution, big investment, it needs huge sums of money. PPP mode is a new financing model and has the inherent driving force to lead the idea the technology and the system innovation. The government and the social subject cooperate on the basis of the spirit of contract thus achieve benefit sharing. This mode effectively improve the operation of new energy vehicle charging facilities operating efficiency

  16. Reliability Considerations for the Operation of Large Accelerator User Facilities

    CERN Document Server

    Willeke, F.J.

    2016-01-01

    The lecture provides an overview of considerations relevant for achieving highly reliable operation of accelerator based user facilities. The article starts with an overview of statistical reliability formalism which is followed by high reliability design considerations with examples. The article closes with operational aspects of high reliability such as preventive maintenance and spares inventory.

  17. 76 FR 62868 - Washington State University; Notice of Issuance of Renewed Facility Operating License No. R-76

    Science.gov (United States)

    2011-10-11

    ...; Notice of Issuance of Renewed Facility Operating License No. R-76 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance of renewed facility operating license No. R- 76. ADDRESSES: You can access.... Nuclear Regulatory Commission (NRC, the Commission) has issued renewed Facility Operating License No. R-76...

  18. Trial operation of the advanced volume reduction facilities for LLW at JAEA

    International Nuclear Information System (INIS)

    Nakashio, Nobuyuki; Higuchi, Hidekazu; Momma, Toshiyuki; Kozawa, Kazushige; Touhei, Toshio; Sudou, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Kou; Ishikawa, Joji; Kato, Mitsugu; Sato, Motoaki

    2007-01-01

    The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level radioactive solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former has cutting installations for large size wastes and the latter has melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750 m 3 and the volume reduction ratio is from 1.7 to 3.7. The WVRF has been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005. (author)

  19. Radiological operating experience at FFTF [Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Bunch, W.L.; Prevo, P.R.

    1986-11-01

    The Fast Flux Test Facility has been in operation for approximately five years, including about one thousand days of full power operation of the Fast Test Reactor. During that time the collective dose equivalents received by operating personnel have been about two orders of magnitude lower than those typically received at commercial light water reactors. No major contamination problems have been encountered in operating and maintaining the plant, and release of radioactive gas to the environment has been minimal and well below acceptable limits. All shields have performed satisfactorily. Experience to date indicates an apparent radiological superiority of liquid metal reactor systems over current light water plants

  20. Underground characterisation and research facility ONKALO

    International Nuclear Information System (INIS)

    Ikonen, Antti; Ylae-Mella, Mia; Aeikaes, Timo

    2006-01-01

    Posiva's repository for geological disposal of the spent fuel from Finnish nuclear reactors will be constructed at Olkiluoto. The selection of Olkiluoto was made based on site selection research programme conducted between 1987-2001. The next step is to carry out complementary investigations of the site and apply for the construction license for the disposal facility. The license application will be submitted in 2012. To collect detailed information of the geological environment at planned disposal depth an underground characterisation and research facility will be built at the site. This facility, named as ONKALO, will comprise a spiral access tunnel and two vertical shafts. The excavation of ONKALO is in progress and planned depth (400 m) will be reached in 2009. During the course of the excavation Posiva will conduct site characterisation activities to assess the structure and other properties of the site geology. The aim is that construction will not compromise the favourable conditions of the planned disposal depth or introduce harmful effects in the surrounding bedrock which could jeopardize the long-term safety of the geological disposal. (author)

  1. Research and test facilities required in nuclear science and technology

    International Nuclear Information System (INIS)

    2009-01-01

    Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy. An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production. This report contains the expert group's detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities. (authors)

  2. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ballinger, Marcel Y.; Gervais, Todd L.

    2004-11-15

    The Pacific Northwest National Laboratory (PNNL) operates a number of Research & Development (R&D) facilities for the U.S. Department of Energy (DOE) on the Hanford Site. Facility effluent monitoring plans (FEMPs) have been developed to document the facility effluent monitoring portion of the Environmental Monitoring Plan (DOE 2000) for the Hanford Site. Three of PNNL’s R&D facilities, the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling, and individual FEMPs were developed for these facilities in the past. In addition, a balance-of-plant (BOP) FEMP was developed for all other DOE-owned, PNNL-operated facilities at the Hanford Site. Recent changes, including shutdown of buildings and transition of PNNL facilities to the Office of Science, have resulted in retiring the 3720 FEMP and combining the 331 FEMP into the BOP FEMP. This version of the BOP FEMP addresses all DOE-owned, PNNL-operated facilities at the Hanford Site, excepting the Radiochemical Processing Laboratory, which has its own FEMP because of the unique nature of the building and operations. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R&D. R&D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in Appendix A. Potential radioactive airborne emissions in the BOP facilities are estimated annually using a building inventory-based approach provided in federal regulations. Sampling at individual BOP facilities is based on a potential-to-emit assessment. Some of these facilities are considered minor emission points and thus are sampled routinely, but not continuously, to confirm the low emission potential. One facility, the 331 Life Sciences Laboratory, has a major emission point and is sampled continuously. Sampling systems are

  3. Facilities available for actinide research in Prague

    International Nuclear Information System (INIS)

    Sechovský, V.

    2014-01-01

    Since June 2012 the Prague group at the Charles University operates a Czech research infrastructure Magnetism and Low Temperature Laboratories (MLTL - http://mltl.eu orhttp://lmnt.cz)which is financially supported by the Government of Czech Republic. The main mission of MLTL is to provide broad scientific community unique possibilities for comprehensive experimental studies of physical phenomena and properties of materials in multiextreme conditions.MLTL offer open access to a wide range of experimental facilities for sample preparation (SSE refinement of staring metals, synthesis of bulk polycrystals, growth of single crystals), characterization (XRD, SEM + EDX) and measurements of various physical properties in high magnetic fields up to 20 T, temperatures from 30 mK to 1000Kand external pressures up to 25 GPa). Anybody can apply for experimental time with his proposal on the user portal of http://mltl.eu. The main strategic objective is the excellence of the infrastructure on the international scale. Therefore the MLTL Panel evaluation the proposals and allocation of experimental time is based primarily on the quality of intended research. The proposals of students for experiments needed for their theses are promoted within the evaluation process. The research opportunities offered by MLTL will be demonstrated during the lecture with emphasis on methodology

  4. Operation of post-irradiation examination facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, E. G.; Jeon, Y. B.; Ku, D. S.

    1996-12-01

    In 1996, the post-irradiation examination(PIE) of nuclear fuels was performed as follows. It has been searched for the caution of defection of defected fuel rods of Youngkwang-4 reactor through NDT and metallographic examination that had been required by KEPCO. And in-pool inspection of Kori-1 spent fuel assembly(FO2) was carried out. HVAC system and pool water treatment system have been operated to maintain the facility safely, and electric power supply system was checked and maintained for the normal and steady supply electric power to the facility. Image processing software was developed for measurement of defection of spent fuel rods. Besides, a radiation shielding glove box was fabricated and a hot cell compressor for volume reduction of radioactive materials was fabricated and installed in hot cell. Safeguards of nuclear materials were implemented in strict accordance with the relevant Korean rules and regulations as well as the international non-proliferation regime. Also the IAEA inspection was carried out on the quarterly basis. (author). 31 tabs., 71 figs., 4 refs.

  5. Zero Gravity Research Facility (Zero-G)

    Data.gov (United States)

    Federal Laboratory Consortium — The Zero Gravity Research Facility (Zero-G) provides a near weightless or microgravity environment for a duration of 5.18 seconds. This is accomplished by allowing...

  6. The Use of Underground Research Laboratories to Support Repository Development Programs. A Roadmap for the Underground Research Facilities Network.

    Energy Technology Data Exchange (ETDEWEB)

    MacKinnon, Robert J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-10-26

    Under the auspices of the International Atomic Energy Agency (IAEA), nationally developed underground research laboratories (URLs) and associated research institutions are being offered for use by other nations. These facilities form an Underground Research Facilities (URF) Network for training in and demonstration of waste disposal technologies and the sharing of knowledge and experience related to geologic repository development, research, and engineering. In order to achieve its objectives, the URF Network regularly sponsors workshops and training events related to the knowledge base that is transferable between existing URL programs and to nations with an interest in developing a new URL. This report describes the role of URLs in the context of a general timeline for repository development. This description includes identification of key phases and activities that contribute to repository development as a repository program evolves from an early research and development phase to later phases such as construction, operations, and closure. This information is cast in the form of a matrix with the entries in this matrix forming the basis of the URF Network roadmap that will be used to identify and plan future workshops and training events.

  7. Accounting control of tritium at the tritium process laboratory (TPL) of JAERI. Results of 15-year operation and research activity

    International Nuclear Information System (INIS)

    Nishi, Masataka; Yamanishi, Toshihiko; Hayashi, Takumi; Yamada, Masayuki; Suzuki, Takumi

    2003-01-01

    Research and development work of fuel processing technology and tritium safe-handling technology necessary for fusion reactors has been performed at the Tritium Process Laboratory (TPL) of JAERI. TPL is the first facility in Japan permitted to handle tritium of more than 1g (about 0.36PBq), and its operation itself is also important for the development of fusion reactor facility in the viewpoint of tritium control. Various experiments have been carried out at TPL safely since 1988 controlling 22PBq of tritium as the maximum observing regulations. In addition to the regulatory accounting and control, detailed independent control in TPL was planned and was established through its 15-year safe-operation. For future fusion fuel facility where kilo-grams of tritium will be handled, method of tritium accounting has been researched and some new technologies have been developed at TPL. Results of TPL operation and of the research activity in it contributed the completion of the engineering design of ITER. Further research activity on tritium accounting and control is in progress in TPL for the future fusion reactors. (author)

  8. Helium turbomachinery operating experience from gas turbine power plants and test facilities

    International Nuclear Information System (INIS)

    McDonald, Colin F.

    2012-01-01

    The closed-cycle gas turbine, pioneered and deployed in Europe, is not well known in the USA. Since nuclear power plant studies currently being conducted in several countries involve the coupling of a high temperature gas-cooled nuclear reactor with a helium closed-cycle gas turbine power conversion system, the experience gained from operated helium turbomachinery is the focus of this paper. A study done as early as 1945 foresaw the use of a helium closed-cycle gas turbine coupled with a high temperature gas-cooled nuclear reactor, and some two decades later this was investigated but not implemented because of lack of technology readiness. However, the first practical use of helium as a gas turbine working fluid was recognized for cryogenic processes, and the first two small fossil-fired helium gas turbines to operate were in the USA for air liquefaction and nitrogen production facilities. In the 1970's a larger helium gas turbine plant and helium test facilities were built and operated in Germany to establish technology bases for a projected future high efficiency large nuclear gas turbine power plant concept. This review paper covers the experience gained, and the lessons learned from the operation of helium gas turbine plants and related test facilities, and puts these into perspective since over three decades have passed since they were deployed. An understanding of the many unexpected events encountered, and how the problems, some of them serious, were resolved is important to avoid them being replicated in future helium turbomachines. The valuable lessons learned in the past, in many cases the hard way, particularly from the operation in Germany of the Oberhausen II 50 MWe helium gas turbine plant, and the technical know-how gained from the formidable HHV helium turbine test facility, are viewed as being germane in the context of current helium turbomachine design work being done for future high efficiency nuclear gas turbine plant concepts. - Highlights:

  9. Holifield Heavy-Ion Research Facility at Oak Ridge

    International Nuclear Information System (INIS)

    Jones, C.M.

    1977-01-01

    A new heavy-ion accelerator facility is now under construction at the Oak Ridge National Laboratory. A brief description of the scope and schedule of this project is given, and the new large tandem accelerator, which will be a major element of the facility is discussed in some detail. Several studies which have been made or are in progress in Oak Ridge in preparation for operation of the tandem accelerator are briefly described

  10. Modelling and operation strategies of DLR's large scale thermocline test facility (TESIS)

    Science.gov (United States)

    Odenthal, Christian; Breidenbach, Nils; Bauer, Thomas

    2017-06-01

    In this work an overview of the TESIS:store thermocline test facility and its current construction status will be given. Based on this, the TESIS:store facility using sensible solid filler material is modelled with a fully transient model, implemented in MATLAB®. Results in terms of the impact of filler site and operation strategies will be presented. While low porosity and small particle diameters for the filler material are beneficial, operation strategy is one key element with potential for optimization. It is shown that plant operators have to ponder between utilization and exergetic efficiency. Different durations of the charging and discharging period enable further potential for optimizations.

  11. Archive of Geosample Data and Information from the Florida State University (FSU) Antarctic Marine Geology Research Facility (AMGRF)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Antarctic Marine Geology Research Facility (AMGRF) operated by Florida State University is a partner in the Index to Marine and Lacustrine Geological Samples...

  12. Design study of underground facility of the Underground Research Laboratory

    International Nuclear Information System (INIS)

    Hibiya, Keisuke; Akiyoshi, Kenji; Ishizuka, Mineo; Anezaki, Susumu

    1998-03-01

    Geoscientific research program to study deep geological environment has been performed by Power Reactor and Nuclear Fuel Development Corporation (PNC). This research is supported by 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. An Underground Research Laboratory is planned to be constructed at Shoma-sama Hora in the research area belonging to PNC. A wide range of geoscientific research and development activities which have been previously studied at the Tono Area is planned in the laboratory. The Underground Research Laboratory is consisted of Surface Laboratory and Underground Research Facility located from the surface down to depth between several hundreds and 1,000 meters. Based on the results of design study in last year, the design study performed in this year is to investigate the followings in advance of studies for basic design and practical design: concept, design procedure, design flow and total layout. As a study for the concept of the underground facility, items required for the facility are investigated and factors to design the primary form of the underground facility are extracted. Continuously, design methods for the vault and the underground facility are summarized. Furthermore, design procedures of the extracted factors are summarized and total layout is studied considering the results to be obtained from the laboratory. (author)

  13. DOE High Performance Computing Operational Review (HPCOR): Enabling Data-Driven Scientific Discovery at HPC Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, Richard; Allcock, William; Beggio, Chris; Campbell, Stuart; Cherry, Andrew; Cholia, Shreyas; Dart, Eli; England, Clay; Fahey, Tim; Foertter, Fernanda; Goldstone, Robin; Hick, Jason; Karelitz, David; Kelly, Kaki; Monroe, Laura; Prabhat,; Skinner, David; White, Julia

    2014-10-17

    U.S. Department of Energy (DOE) High Performance Computing (HPC) facilities are on the verge of a paradigm shift in the way they deliver systems and services to science and engineering teams. Research projects are producing a wide variety of data at unprecedented scale and level of complexity, with community-specific services that are part of the data collection and analysis workflow. On June 18-19, 2014 representatives from six DOE HPC centers met in Oakland, CA at the DOE High Performance Operational Review (HPCOR) to discuss how they can best provide facilities and services to enable large-scale data-driven scientific discovery at the DOE national laboratories. The report contains findings from that review.

  14. Environmental assessment as a planning tool for the decommissioning of a nuclear research facility in Canada

    International Nuclear Information System (INIS)

    Klukas, M.H.; Grondin, D.J.; Helbrecht, R.A.

    2002-01-01

    Whiteshell Laboratories, a nuclear research facility operated by Atomic Energy of Canada Ltd. (AECL), have provided research facilities for the Canadian Nuclear Industry since the early 1960's. In 1997, AECL made a business decision to discontinue research programs and operations at the laboratories. Shortly thereafter the decision was made in agreement with the Federal Government of Canada to decommission the laboratories. In compliance with its own policy and to meet the requirements of the Canadian Legislation, AECL assessed the potential environmental effects of the project. The Environmental Assessment included studies to evaluate he feasibility of leaving two major project components in place; low-level radioactive waste in trenches located at the Whiteshell Laboratories site and river sediments contaminated from operational effluent releases. For both project components, it was determined that managing the wastes in the existing location was environmentally sound. An extensive follow-up program, comprising of additional monitoring and analysis to verify these findings will be implemented. As a result of these assessments and the assessments for other project components it was concluded that the project was not likely to cause significant adverse effects. The assessment decision was accepted by the Minister of the Environment in 2002 April. (author)

  15. Operating manual for the High Flux Isotope Reactor. Description of the facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    1965-06-01

    This report contains a comprehensive description of the High Flux Isotope Reactor facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procedures are presented in another report.

  16. National Ignition Facility Control and Information System Operational Tools

    International Nuclear Information System (INIS)

    Marshall, C.D.; Beeler, R.G.; Bowers, G.A.; Carey, R.W.; Fisher, J.M.; Foxworthy, C.B.; Frazier, T.M.; Mathisen, D.G.; Lagin, L.J.; Rhodes, J.J.; Shaw, M.J.

    2009-01-01

    The National Ignition Facility (NIF) in Livermore, California, is the world's highest-energy laser fusion system and one of the premier large scale scientific projects in the United States. The system is designed to setup and fire a laser shot to a fusion ignition or high energy density target at rates up to a shot every 4 hours. NIF has 192 laser beams delivering up to 1.8 MJ of energy to a ∼2 mm target that is planned to produce >100 billion atm of pressure and temperatures of >100 million degrees centigrade. NIF is housed in a ten-story building footprint the size of three football fields as shown in Fig. 1. Commissioning was recently completed and NIF will be formally dedicated at Lawrence Livermore National Laboratory on May 29, 2009. The control system has 60,000 hardware controls points and employs 2 million lines of control system code. The control room has highly automated equipment setup prior to firing laser system shots. This automation has a data driven implementation that is conducive to dynamic modification and optimization depending on the shot goals defined by the end user experimenters. NIF has extensive facility machine history and infrastructure maintenance workflow tools both under development and deployed. An extensive operational tools suite has been developed to support facility operations including experimental shot setup, machine readiness, machine health and safety, and machine history. The following paragraphs discuss the current state and future upgrades to these four categories of operational tools.

  17. Design and operation of radiation facilities

    International Nuclear Information System (INIS)

    Gay, H.G.

    1983-01-01

    The design, manufacture, and operation of Cobalt-60 Radiation Processing Facilities is a well established technology. However, the products requiring radiation processing are constantly increasing. Product and dose variations create different requirements in the irradiator design. Several basic design concepts which have been developed and installed by Atomic Energy of Canada Limited are discussed. Irradiators are most efficient when designed to handle a limited product density range at an established dose. Requirements for irradiators to process a multitude of different products at different doses leads to a reduction of irradiator efficiency with resultant increase in processing costs

  18. New methods and techniques for decontamination in maintenance or decommissioning operations. Results of a co-ordinated research programme 1994-1998

    International Nuclear Information System (INIS)

    1998-06-01

    Decontamination of nuclear facilities is a subject of increasing importance as the nuclear community considers the issues related to the decommissioning of surplus or obsolete facilities and making modifications to operational facilities, or conducts the necessary inspections and maintenance to permit continued efficient and safe operation of existing facilities. Previous co-ordinated research programmes (CRP) conducted respectively from 1984 to 1987, and from 1989 to 1993, highlighted the role of decontamination within the overall domain of decommissioning. Having recognized technological progress in decontamination and the large potential for optimization, the CRP on New Methods and Techniques for Optimization of Decontamination for Maintenance or Decommissioning was launched and conducted by the IAEA from 1994 to 1998. Concluding reports that summarized the work undertaken under the aegis of the CRP were presented at the third and final Research Co-ordination Meeting (RCM) held in Mol, Belgium, 12-16 January 1998 and are collected in this Technical Document. Operating experience in real-scale applications, lessons learned, key results in laboratory scale or pilot scale research, and validation of mathematical models, are among the most significant achievements of the CRP and have been highlighted

  19. Operator training facilities for CEGB advanced gas cooled reactors

    International Nuclear Information System (INIS)

    Green, J.F.; Birnie, S.

    1980-01-01

    The facilities provided at the Nuclear Power Training Centre of the CEGB for the training of operators fo the AGR are described. The simulator control desks are replicas of three AGR designs with, in addition, simulation of the Data Processing System for each station. Three modes of operation are envisaged: a.) Demonstration where the simulator is used by the tutor to illustrate lecture on plant behaviour. b.) Interaction where the student carries out normal procedures and experiences plant failure situations. c.) Investigation where engineering staff use the simulator for validation of modified operational procedures, ergonomic studies etc. (orig./HP)

  20. ARM Operations and Engineering Procedure Mobile Facility Site Startup

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, Jimmy W

    2015-05-01

    This procedure exists to define the key milestones, necessary steps, and process rules required to commission and operate an Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF), with a specific focus toward on-time product delivery to the ARM Data Archive. The overall objective is to have the physical infrastructure, networking and communications, and instrument calibration, grooming, and alignment (CG&A) completed with data products available from the ARM Data Archive by the Operational Start Date milestone.

  1. Regulation for installation and operation of experimental-research reactor

    International Nuclear Information System (INIS)

    1979-01-01

    The ordinance is stipulated under the Law for regulation of nuclear raw materials, nuclear fuel materials and reactors and the provisions for installation and operation of reactor in the order for execution of the law. Basic concepts and terms are defined, such as, radioactive waste; fuel assembly; exposure dose; accumulative dose; controlled area; preserved area; inspected surrounding area and employee. An application for permission of installation of reactor shall list such matters as: the maximum continuous thermal output of reactor; location and general construction of reactor facilities; construction and equipment of the main reactor and other facilities for nuclear fuel materials; cooling and controlling system and radioactive waste, etc. An operation plan of reactor for three years shall be filed till January 31 of the fiscal year preceding that one the operation begins. Records shall be made and kept for specified periods respectively on inspection of reactor facilities, operation, fuel assembly, radiation control, maintenance, accidents of reactor equipment and weather. Detailed rules are settled for entrance limitation to controlled area, exposure dose, inspection, check up and regular independent examination of reactor facilities, operation of reactor, transportation of substances contaminated by nuclear fuel materials within the works and storage, etc. (Okada, K.)

  2. YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety

    International Nuclear Information System (INIS)

    Mattila, L.; Vanttola, T.

    1992-01-01

    The major part of nuclear energy research in Finland has been organised as five-year nationally coordinated research programs. The research programme on Systems Behaviour and Operational Aspects of Safety is under way during 1990-1994. Its annual volume has been about 35 person-years and its annual expenditure about FIM 18 million. Studies in the field on safe operational margins of nuclear fuel and reactor core concentrate on fuel high burn-up behaviour, VVER fuel experiments, and reactor core behaviour in complex reactivity transients such as 3-D phenomena and ATWS events. The PACTEL facility is used for the thermal hydraulic studies of the Loviisa type reactors (scaled 1:305). Validation of accident analysis codes is carried out by participation in international standard problems. Advanced foreign computer codes for severe reactor accidents are implemented, modified as needed and applied to level-2 PSAs and the improvement of accident management procedures. Fire simulation methods are tested using data from experiments in the German HDR facility. A nuclear plant analyzer for efficient safety analyses is being developed using the APROS process simulation environment. Computerized operator support systems are being studied in cooperation with the OECD Halden Project. The basic factors affecting plant operator activities and the development of their competence are being investigated. A comprehensive system for the control of plant operational safety is being developed by combining living PSA and safety indicators

  3. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs.

  4. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    International Nuclear Information System (INIS)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs

  5. How Large-Scale Research Facilities Connect to Global Research

    DEFF Research Database (Denmark)

    Lauto, Giancarlo; Valentin, Finn

    2013-01-01

    Policies for large-scale research facilities (LSRFs) often highlight their spillovers to industrial innovation and their contribution to the external connectivity of the regional innovation system hosting them. Arguably, the particular institutional features of LSRFs are conducive for collaborative...... research. However, based on data on publications produced in 2006–2009 at the Neutron Science Directorate of Oak Ridge National Laboratory in Tennessee (United States), we find that internationalization of its collaborative research is restrained by coordination costs similar to those characterizing other...

  6. Decontamination and recovery of a nuclear facility to allow continued operation

    International Nuclear Information System (INIS)

    Cavaghan, Josh

    2017-01-01

    A power supply failure caused a loss of power to key ventilation systems in an operating nuclear facility. The in-cell depression was lost, which led to an egress of activity through prepared areas and into the normal operating areas. After an initial programme of radiological monitoring to quantify and categorise the activity in the operating areas, a plan was developed for the decontamination and remediation of the plant. The scope of the recovery plan was substantial and featured several key stages. The contamination was almost entirely "1"3"7Cs, reflecting the α:β/γ ratio for the facility. In addition to the physical remediation work, several administrative controls were introduced such as new local rules, safety signage to indicate abnormal radiological conditions in certain areas and training of the decontamination teams. All areas of plant, which were contaminated, were returned to normal access arrangements and the plant was successfully returned to full operational capability, <12 months from the date of the event. (authors)

  7. Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

    Energy Technology Data Exchange (ETDEWEB)

    Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

    1991-12-31

    This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}. Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

  8. Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

    Energy Technology Data Exchange (ETDEWEB)

    Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

    1991-12-31

    This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}, Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

  9. Advanced reactor experimental facilities

    International Nuclear Information System (INIS)

    Amri, A.; Papin, J.; Uhle, J.; Vitanza, C.

    2010-01-01

    For many years, the NEA has been examining advanced reactor issues and disseminating information of use to regulators, designers and researchers on safety issues and research needed. Following the recommendation of participants at an NEA workshop, a Task Group on Advanced Reactor Experimental Facilities (TAREF) was initiated with the aim of providing an overview of facilities suitable for carrying out the safety research considered necessary for gas-cooled reactors (GCRs) and sodium fast reactors (SFRs), with other reactor systems possibly being considered in a subsequent phase. The TAREF was thus created in 2008 with the following participating countries: Canada, the Czech Republic, Finland, France, Germany, Hungary, Italy, Japan, Korea and the United States. In a second stage, India provided valuable information on its experimental facilities related to SFR safety research. The study method adopted entailed first identifying high-priority safety issues that require research and then categorizing the available facilities in terms of their ability to address the safety issues. For each of the technical areas, the task members agreed on a set of safety issues requiring research and established a ranking with regard to safety relevance (high, medium, low) and the status of knowledge based on the following scale relative to full knowledge: high (100%-75%), medium (75 - 25%) and low (25-0%). Only the issues identified as being of high safety relevance and for which the state of knowledge is low or medium were included in the discussion, as these issues would likely warrant further study. For each of the safety issues, the TAREF members identified appropriate facilities, providing relevant information such as operating conditions (in- or out-of reactor), operating range, description of the test section, type of testing, instrumentation, current status and availability, and uniqueness. Based on the information collected, the task members assessed prospects and priorities

  10. System Security Authorization Agreement (SSAA) for the WIRE Archive and Research Facility

    Science.gov (United States)

    2002-01-01

    The Wide-Field Infrared Explorer (WIRE) Archive and Research Facility (WARF) is operated and maintained by the Department of Physics, USAF Academy. The lab is located in Fairchild Hall, 2354 Fairchild Dr., Suite 2A103, USAF Academy, CO 80840. The WARF will be used for research and education in support of the NASA Wide Field Infrared Explorer (WIRE) satellite, and for related high-precision photometry missions and activities. The WARF will also contain the WIRE preliminary and final archives prior to their delivery to the National Space Science Data Center (NSSDC). The WARF consists of a suite of equipment purchased under several NASA grants in support of WIRE research. The core system consists of a Red Hat Linux workstation with twin 933 MHz PIII processors, 1 GB of RAM, 133 GB of hard disk space, and DAT and DLT tape drives. The WARF is also supported by several additional networked Linux workstations. Only one of these (an older 450 Mhz PIII computer running Red Hat Linux) is currently running, but the addition of several more is expected over the next year. In addition, a printer will soon be added. The WARF will serve as the primary research facility for the analysis and archiving of data from the WIRE satellite, together with limited quantities of other high-precision astronomical photometry data from both ground- and space-based facilities. However, the archive to be created here will not be the final archive; rather, the archive will be duplicated at the NSSDC and public access to the data will generally take place through that site.

  11. Operating manual for the Tower Shielding Facility

    International Nuclear Information System (INIS)

    1985-12-01

    This manual provides information necessary to operate and perform maintenance on the reactor systems and all equipment or systems which can affect their operation or the safety of personnel at the Tower Shielding Facility. The first four chapters consist of introductory and descriptive material of benefit to personnel in training, the qualifications required for training, the responsibilities of the personnel in the organization, and the procedures for reviewing proposed experiments. Chapter 8, Emergency Procedures, is also a necessary part of the indoctrination of personnel. The procedures for operation of the Tower Shielding Reactor (TSR-II), its water cooling system, and the main tower hoists are outlined in Chapters 5, 6, and 7. The Technical Specification surveillance requirements for the TSR-II are summarized in Chapter 9. The maintenance and calibration schedule is spelled out in Chapter 10. The procedures for assembly and disassembly of the TSR-II are outlined in Chapter 11

  12. Irradiation Facilities of the Takasaki Advanced Radiation Research Institute

    Directory of Open Access Journals (Sweden)

    Satoshi Kurashima

    2017-03-01

    Full Text Available The ion beam facility at the Takasaki Advanced Radiation Research Institute, the National Institutes for Quantum and Radiological Science and Technology, consists of a cyclotron and three electrostatic accelerators, and they are dedicated to studies of materials science and bio-technology. The paper reviews this unique accelerator complex in detail from the viewpoint of its configuration, accelerator specification, typical accelerator, or irradiation technologies and ion beam applications. The institute has also irradiation facilities for electron beams and 60Co gamma-rays and has been leading research and development of radiation chemistry for industrial applications in Japan with the facilities since its establishment. The configuration and utilization of those facilities are outlined as well.

  13. Operational experiences in radiation protection in fast reactor fuel reprocessing facility

    International Nuclear Information System (INIS)

    Meenakshisundaram, V.; Rajagopal, V.; Santhanam, R.; Baskar, S.; Madhusoodanan, U.; Chandrasekaran, S.; Balasundar, S.; Suresh, K.; Ajoy, K.C.; Dhanasekaran, A.; Akila, R.; Indira, R.

    2008-01-01

    The Compact Reprocessing facility for Advanced fuels in Lead cells (CORAL), situated at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam is a pilot plant to reprocess the mixed carbide fuel, for the first time in the world. Reprocessing of fuel with varying burn-ups up to 155 G Wd/t, irradiated at Fast Breeder Test Reactor (FBTR), has been successfully carried out at CORAL. Providing radiological surveillance in a fuel reprocessing facility itself is a challenging task, considering the dynamic status of the sources and the proximity of the operator with the radioactive material and it is more so in a fast reactor fuel reprocessing facility due to handling of higher burn-up fuels associated with radiation fields and elevated levels of fissile material content from the point of view of criticality hazard. A very detailed radiation protection program is in place at CORAL. This includes, among others, monitoring the release of 85 Kr and other fission products and actinides, if any, through stack on a continuous basis to comply with the regulatory limits and management of disposal of different types of radioactive wastes. Providing radiological surveillance during the operations such as fuel transport, chopping and dissolution and extraction cycle was without any major difficulty, as these were carried out in well-shielded and high integrity lead cells. Enforcement of exposure control assumes more importance during the analysis of process samples and re-conversion operations due to the presence of fission product impurities and also since the operations were done in glove boxes and fume hoods. Although the radiation fields encountered in process area were marginally higher, due to the enforcement of strict administrative controls, the annual exposure to the radiation workers was well within the regulatory limit. As the facility is being used as test bed for validation of prototype equipment, periodic inspection and maintenance of components such as centrifuge

  14. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

  15. Map of gas facilities and operators in Northeast British Columbia

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2005-06-01

    This map represents 57 gas facilities and operators and references location on the map to the facility and operator. The Northern Rockies Regional district is indicated, as is the Peace River Regional district. Roads, truck trails, railroads, pipeline and airstrips are indicated as well as oil and gas fields. Various protected areas and First Nations settlement areas and regions are also indicated. The following companies placed advertisements on the map, detailing the services they provide: Wellco Energy Services; C.E. Franklin Ltd.; the City of Fort St. John, Region of Chetwynd; Smith Bits; the City of Dawson Creek, Economic Development and Tourism; Fort Nelson and Northern Rockies Regional District; Pipetech Corp.; Kenwood; Hughes Christensen; Spartan Controls; FI Canada Oil Services Ltd.; Northstar Drillstem Testers Inc.; Rainbow Transport Ltd.1 fig.

  16. The SARAF Project - Soreq Applied Research Accelerator Facility

    International Nuclear Information System (INIS)

    Nagler, A.; Mardor, I.; Berkovits, D.; Piel, C.

    2004-01-01

    The relevance of particle accelerators to society, in the use of their primary and secondary beams for the analysis of physical, chemical and biological samples and for modification of properties of materials, is well recognized and documented. Nevertheless, apart of the construction of small accelerators for nuclear research in the 1960's and 70's, Israel has so far neglected this important and growing field. Furthermore, there is an urgent need in Israel for a state of the art research facility to attract and introduce students to current advanced physics techniques and technologies and to train the next generation of experimental scientists in various branches and disciplines. Therefore, Soreq NRC recently initiated the establishment of a new accelerator facility, named SARAF Soreq Applied Research Accelerator Facility. SARAF will be a continuous wave (CW), proton and deuteron RF superconducting linear accelerator with variable energy (5 - 40 MeV) and current (0.04 -2 mA). SARAF is designed to enable hands-on maintenance, which means that its beam loss will be below 10 -5 for the entire accelerator. These specifications will place SARAF in line with the next generation of accelerators world wide. Soreq expects that this fact will attract the Israeli and international research communities to use this facility extensively. Soreq NRC intends to use SARAF for basic, medical and biological research, and non-destructive testing (NDT). Another major activity will be the research and development of radio-isotopes production techniques. Given the availability of high current (up to 2 mA) protons and deuterons, a major activity will be research and development of high power density (up to 80 kW on a few cm 2 ) irradiation targets

  17. Report of the research results with JAERI's facilities in fiscal 1975

    International Nuclear Information System (INIS)

    1976-07-01

    Results of the research works by educational institutions using facilities of the Japan Atomic Energy Research Institute in fiscal 1975 are reported in individual summaries. Facilities utilized are research reactors, Co-60 irradiation facilities, hot laboratory, Linac and electron accelerators. Fields of research are the following: nuclear physics, radiation damage/solid-state physics, positron annihilation, activation analysis/nuclear chemistry, hot atom chemistry, irradiation effects, biology, and neutron diffraction; and, cooperative works to JAERI. (Mori, K.)

  18. Atmospheric Radiation Measurement (ARM) Climate Research Facility Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mather, James [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-04-01

    Mission and Vision Statements for the U.S. Department of Energy (DOE)’s Atmospheric Radiation Measurement (ARM) Climate Research Facility Mission The ARM Climate Research Facility, a DOE scientific user facility, provides the climate research community with strategically located in situ and remote-sensing observatories designed to improve the understanding and representation, in climate and earth system models, of clouds and aerosols as well as their interactions and coupling with the Earth’s surface. Vision To provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes to resolve the uncertainties in climate and Earth system models toward the development of sustainable solutions for the nation's energy and environmental challenges.

  19. FAIR - Facility, Research Program and Status of the Project

    International Nuclear Information System (INIS)

    Majka, Z.

    2011-01-01

    The international Facility for Antiproton and Ion Research (FAIR) in Europe will provide a worldwide science community with a unique and technically innovative accelerator system to perform forefront research in the sciences concerned with the basic structure of matter, and in intersections with other fields. The facility will deliver an extensive range of primary and secondary particle beams from protons and their antimatter partners, antiprotons, to ion beams of all chemical elements up to the heaviest, uranium, with in many respects unique properties and intensities. The paper will include overview of the new facility design and research programs to be carried out there. The current status of the FAIR project will be also presented. (author)

  20. A new facility for advanced rocket propulsion research

    Science.gov (United States)

    Zoeckler, Joseph G.; Green, James M.; Raitano, Paul

    1993-06-01

    A new test facility was constructed at the NASA Lewis Research Center Rocket Laboratory for the purpose of conducting rocket propulsion research at up to 8.9 kN (2000 lbf) thrust, using liquid oxygen and gaseous hydrogen propellants. A laser room adjacent to the test cell provides access to the rocket engine for advanced laser diagnostic systems. The size and location of the test cell provide the ability to conduct large amounts of testing in short time periods, with rapid turnover between programs. These capabilities make the new test facility an important asset for basic and applied rocket propulsion research.

  1. Initial closed operation of the CELSS Test Facility Engineering Development Unit

    Science.gov (United States)

    Kliss, M.; Blackwell, C.; Zografos, A.; Drews, M.; MacElroy, R.; McKenna, R.; Heyenga, A. G.

    2003-01-01

    As part of the NASA Advanced Life Support Flight Program, a Controlled Ecological Life Support System (CELSS) Test Facility Engineering Development Unit has been constructed and is undergoing initial operational testing at NASA Ames Research Center. The Engineering Development Unit (EDU) is a tightly closed, stringently controlled, ground-based testbed which provides a broad range of environmental conditions under which a variety of CELSS higher plant crops can be grown. Although the EDU was developed primarily to provide near-term engineering data and a realistic determination of the subsystem and system requirements necessary for the fabrication of a comparable flight unit, the EDU has also provided a means to evaluate plant crop productivity and physiology under controlled conditions. This paper describes the initial closed operational testing of the EDU, with emphasis on the hardware performance capabilities. Measured performance data during a 28-day closed operation period are compared with the specified functional requirements, and an example of inferring crop growth parameters from the test data is presented. Plans for future science and technology testing are also discussed. Published by Elsevier Science Ltd on behalf of COSPAR.

  2. Integrated safeguards and facility design and operations

    International Nuclear Information System (INIS)

    Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

    1987-01-01

    The integration of safeguards functions to deter or detect unauthorized actions by an insider requires the careful communication and management of safeguards-relevant information on a timely basis. The traditional separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification, and careful attention to management of information from acquisition to organization, to analysis, to decision making can result in effective safeguards integration. The careful inclusion of these ideas in facility designs and operations will lead to cost-effective safeguards systems. The safeguards authorization function defines, for example, personnel access requirements, processing activities, and materials movements/locations that are permitted to accomplish the mission of the facility. Minimizing the number of authorized personnel, limiting the processing flexibility, and maintaining up-to-date flow sheets will facilitate the detection of unauthorized activities. Enforcement of the authorized activities can be achieved in part through the use of barriers, access control systems, process sensors, and health and safety information. Consideration of safeguards requirements during facility design can improve the enforcement function. Verification includes the familiar materials accounting activities as well as auditing and testing of the other functions

  3. Accounting and Control of Tritium at the Tritium Process Laboratory (TPL) of JAERI - Results of 15-year Operation and Research Activity -

    Science.gov (United States)

    Nishi, Masataka; Yamanishi, Toshihiko; Hayashi, Takumi; Yamada, Masayuki; Suzuki, Takumi

    Research and development work of fuel processing technology and tritium safe-handling technology necessary for fusion reactors has been performed at the Tritium Process Laboratory (TPL) of JAERI. TPL is the first facility in Japan permitted to handle tritium of more than 1g (about 0.36PBq), and its operation itself is also important for the development of fusion reactor facility in the viewpoint of tritium control. Various experiments have been carried out at TPL safely since 1988 controlling 22PBq of tritium as the maximum observing regulations. In addition to the regulatory accounting and control, detailed independent control in TPL was planned and was established throughits15-yearsafe-operation. For future fusion fuel facility where kilograms of tritium will be handled, method of tritium accounting has been researched and some new technologies have been developed at TPL. Results of TPL operation and of the research activity in it contributed the completion of the engineering design of ITER. Further research activity on tritium accounting and control is in progress in TPL for the future fusion reactors.

  4. STAR facility tritium accountancy

    International Nuclear Information System (INIS)

    Pawelko, R. J.; Sharpe, J. P.; Denny, B. J.

    2008-01-01

    The Safety and Tritium Applied Research (STAR) facility has been established to provide a laboratory infrastructure for the fusion community to study tritium science associated with the development of safe fusion energy and other technologies. STAR is a radiological facility with an administrative total tritium inventory limit of 1.5 g (14,429 Ci) [1]. Research studies with moderate tritium quantities and various radionuclides are performed in STAR. Successful operation of the STAR facility requires the ability to receive, inventory, store, dispense tritium to experiments, and to dispose of tritiated waste while accurately monitoring the tritium inventory in the facility. This paper describes tritium accountancy in the STAR facility. A primary accountancy instrument is the tritium Storage and Assay System (SAS): a system designed to receive, assay, store, and dispense tritium to experiments. Presented are the methods used to calibrate and operate the SAS. Accountancy processes utilizing the Tritium Cleanup System (TCS), and the Stack Tritium Monitoring System (STMS) are also discussed. Also presented are the equations used to quantify the amount of tritium being received into the facility, transferred to experiments, and removed from the facility. Finally, the STAR tritium accountability database is discussed. (authors)

  5. Research facility access & science education

    Energy Technology Data Exchange (ETDEWEB)

    Rosen, S.P. [Univ. of Texas, Arlington, TX (United States); Teplitz, V.L. [Southern Methodist Univ., Dallas, TX (United States). Physics Dept.

    1994-10-01

    As Congress voted to terminate the Superconducting Super Collider (SSC) Laboratory in October of 1993, the Department of Energy was encouraged to maximize the benefits to the nation of approximately $2 billion which had already been expended to date on its evolution. Having been recruited to Texas from other intellectually challenging enclaves around the world, many regional scientists, especially physicists, of course, also began to look for viable ways to preserve some of the potentially short-lived gains made by Texas higher education in anticipation of {open_quotes}the SSC era.{close_quotes} In fact, by November, 1993, approximately 150 physicists and engineers from thirteen Texas universities and the SSC itself, had gathered on the SMU campus to discuss possible re-uses of the SSC assets. Participants at that meeting drew up a petition addressed to the state and federal governments requesting the creation of a joint Texas Facility for Science Education and Research. The idea was to create a facility, open to universities and industry alike, which would preserve the research and development infrastructure and continue the educational mission of the SSC.

  6. Operational safety assessment of underground test facilities for mined geologic waste disposal

    International Nuclear Information System (INIS)

    Elder, H.K.

    1993-01-01

    This paper describes the operational safety assessment for the underground facilities for the exploratory studies facility (ESF) at the Yucca Mountain Project. The systematic identification and evaluation of hazards related to the ESF is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach based on the analysis of potential accidents was used since radiological safety analysis was not required. The risk assessment summarized credible accident scenarios and the design provides mitigation of the risks to a level that the facility can be constructed and operated with an adequate level of safety. The risk assessment also provides reasonable assurance that all identifiable major accident scenarios have been reviewed and design mitigation features provided to ensure an adequate level of safety

  7. Experimental Facilities Division. Progress report 1996-97

    International Nuclear Information System (INIS)

    1997-04-01

    This progress report summarizes the activities of the Experimental Facilities Division (XFD) in support of the users of the Advanced Photon Source (APS), primarily focusing on the past year of operations. In September 1996, the APS began operations as a national user facility serving the US community of x-ray researchers from private industry, academic institutions, and other research organizations. The start of operations was about three months ahead of the baseline date established in 1988. This report is divided into the following sections: (1) overview; (2) user operations; (3) user administration and technical support; (4) R and D in support of view operations; (5) collaborative research; and (6) long-term strategic plans for XFD

  8. Experimental Facilities Division progress report 1996--97

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This progress report summarizes the activities of the Experimental Facilities Division (XFD) in support of the users of the Advanced Photon Source (APS), primarily focusing on the past year of operations. In September 1996, the APS began operations as a national user facility serving the US community of x-ray researchers from private industry, academic institutions, and other research organizations. The start of operations was about three months ahead of the baseline date established in 1988. This report is divided into the following sections: (1) overview; (2) user operations; (3) user administration and technical support; (4) R and D in support of view operations; (5) collaborative research; and (6) long-term strategic plans for XFD.

  9. Operational Research(ers in development: Growing a new generation of operational researchers

    Directory of Open Access Journals (Sweden)

    I Durbach

    2013-06-01

    Full Text Available This paper explores the theme of training operational research (OR practitioners in South Africa by critically evaluating a Masters program in Operational Research in Development (ORD, launched in 2005 at the University of Cape Town. This program was specifically focused on applying OR to the problems of the developing world in general and Africa in particular. We describe the program and review the practical work undertaken by students participating in the program. Topics range widely across domains including health (antimalarial drug resistance; poverty (food banking; governance (NGO management structures and monitoring of local government performance and sustainable livelihoods (spaza shop operations. We use the review to highlight strengths and weaknesses of the program, as well as challenges faced in the OR education in South Africa at a postgraduate level.

  10. Status of RIB facilities in Asia

    International Nuclear Information System (INIS)

    Tanihata, Isao

    1998-01-01

    Radioactive Ion Beam Facilities in Asia are presented. In China, in-flight separation type facilities are in operation at the Institute of Modern Physics in Lanzhou and the other at Tandem facility in China Institute of Atomic Energy in Beijing. The storage-ring facility is proposed and approved in Lanzhou. In India, the Variable Energy Cyclotron Facility in Calcutta start to construct an ISOL-type facility. In Japan, in-flight separation type facilities are working at Research Center for Nuclear Physics in Osaka, and at RIKEN. Also a separator start its operation in medical facility in Chiba. In RIKEN, the construction of RI Beam Factory has been started. An ISOL-type facility is proposed in the Japan Hadron Facility in KEK. Table I summarize these facilities

  11. Assessment of Radionuclides Release from Inshas LILW Disposal Facility Under Normal and Unusual Operational Conditions

    International Nuclear Information System (INIS)

    Zaki, A.A.

    2008-01-01

    Disposing of low and intermediate radioactive waste (LILW) is a big concern for Egypt due to the accumulated waste as a result of past fifty years of peaceful nuclear applications. Assessment of radionuclides release from Inshas LILW disposal facility under normal and unusual operational conditions is very important in order to apply for operation license of the facility. Aqueous release of radionuclides from this disposal facility is controlled by water flow, access of the water to the wasteform, release of the radionuclides from the wasteform, and transport to the disposal facility boundary. In this work, the release of 137 Cs , 6C o, and 90 Sr radionuclides from the Inshas disposal facility was studied under the change of operational conditions. The release of these radio contaminants from the source term to the unsaturated and saturated zones , to groundwater were studied. It was found that the concentration of radionuclides in a groundwater well located 150 m away from the Inshas disposal facility is less than the maximum permissible concentration in groundwater in both cases

  12. Operation and Maintenance Manual for the Central Facilities Area Sewage Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Norm Stanley

    2011-02-01

    This Operation and Maintenance Manual lists operator and management responsibilities, permit standards, general operating procedures, maintenance requirements and monitoring methods for the Sewage Treatment Plant at the Central Facilities Area at the Idaho National Laboratory. The manual is required by the Municipal Wastewater Reuse Permit (LA-000141-03) the sewage treatment plant.

  13. Experimental evaluation of emergency operating procedures on multiple steam generator tube rupture in INER integral system test facility

    International Nuclear Information System (INIS)

    Liu, T.J.; Lin, Y.M.; Lee, C.H.; Chang, C.Y.; Hong, W.T.

    1997-01-01

    The multiple steam generator tube rupture (SGTR) scenario in Westinghouse type pressurized water reactor (PWR) has been investigated at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility. This reduced-height and reduced-pressure test facility was designed to simulate the main features of Maanshan nuclear power plant. The SGTR test scenario assumes the double-ended break of one-, two- and six- tubes without other failures. The major operator actions follow the related symptom-oriented Emergency Operating Procedure (EOP) on the reference plant. This study focuses on the investigation of thermal-hydraulics phenomena and the adequacy of associated EOP to limit primary-to-secondary leakage. Through this study, it is found that the adequacy of current EOP in minimizing the radioactivity release demands early substantial operator involvement, especially in the multi-tubes break events. Also, the detailed mechanism of the main thermal-hydraulic phenomena during the SGTR transient are explored. (author)

  14. Business applications of operations research

    CERN Document Server

    Nag, Bodhibrata

    2014-01-01

    Operations Research is a bouquet of mathematical techniques which have evolved over the last six decades, to improve the process of business decision making. Operations Research offers tools to optimize and find the best solutions to myriad decisions that managers have to take in their day to day operations or while carrying out strategic planning. Today, with the advent of operations research software, these tools can be applied by managers even without any knowledge of the mathematical techniques that underlie the solution procedures. The book starts with a brief introduction to various tools of operations research, such as linear programming, integer programming, multi-objective programming, queuing theory and network theory together with simple examples in each of the areas. Another introductory chapter on handling the operations research software, along with examples is also provided. The book intends to make the readers aware of the power and potential of operations research in addressing decision makin...

  15. Guidelines for operator competence - Optimising facility management processes; Leitfaden Betreiberkompetenz. Schritt fuer Schritt Facility Management Prozesse optimieren

    Energy Technology Data Exchange (ETDEWEB)

    Moser, R

    2005-06-15

    This brochure issued by IFMA (International Facility Management Association) Switzerland and the Swiss Federal Office of Energy (SFOE) presents interactive guidelines for energy management in the area of facility management. These guidelines are based on the results of a project carried out by the International Energy Agency's Annex 40 'Operator competence'. The guidelines provide a step-by-step guide from initial analysis through to successful project completion and answer many questions that may crop up during the process. The focus is placed on energy aspects. Tools and 14 sample process descriptions are provided along with practical examples. Theoretical aspects are also presented and discussed, including models for operator roles and the processes involved. Also, change, risk and knowledge management are examined. Notes and information on possibilities for further education are presented.

  16. Guidelines for operator competence - Optimising facility management processes; Leitfaden Betreiberkompetenz. Schritt fuer Schritt Facility Management Prozesse optimieren

    Energy Technology Data Exchange (ETDEWEB)

    Moser, R.

    2005-06-15

    This brochure issued by IFMA (International Facility Management Association) Switzerland and the Swiss Federal Office of Energy (SFOE) presents interactive guidelines for energy management in the area of facility management. These guidelines are based on the results of a project carried out by the International Energy Agency's Annex 40 'Operator competence'. The guidelines provide a step-by-step guide from initial analysis through to successful project completion and answer many questions that may crop up during the process. The focus is placed on energy aspects. Tools and 14 sample process descriptions are provided along with practical examples. Theoretical aspects are also presented and discussed, including models for operator roles and the processes involved. Also, change, risk and knowledge management are examined. Notes and information on possibilities for further education are presented.

  17. Paul Scherrer Institute Scientific and Technical Report 1999. Volume VI: Large Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Meyer, Rosa [eds.

    2000-07-01

    The department GFA (Grossforschungsanlagen, Large Research Facilities) has been established in October 1998. Its main duty is operation, maintenance and development of the PSI accelerators, the spallation neutron source and the beam transport systems for pions and muons. A large effort of this group concerns the planning and co-ordination of new projects like e.g. the assembly of the synchrotron light source (SLS), design studies of a new proton therapy facility, the ultracold neutron source and a new intensive secondary beam line for low energy muons. A large fraction of this report is devoted to research especially in the field of materials Science. The studies include large scale molecular dynamics computer simulations on the elastic and plastic behavior of nanostructured metals, complemented by experimental mechanical testing using micro-indentation and miniaturized tensile testing, as well as microstructural characterisation and strain field mapping of metallic coatings and thin ceramic layers, the latter done with synchrotron radiation.

  18. Paul Scherrer Institute Scientific and Technical Report 1999. Volume VI: Large Research Facilities

    International Nuclear Information System (INIS)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Meyer, Rosa

    2000-01-01

    The department GFA (Grossforschungsanlagen, Large Research Facilities) has been established in October 1998. Its main duty is operation, maintenance and development of the PSI accelerators, the spallation neutron source and the beam transport systems for pions and muons. A large effort of this group concerns the planning and co-ordination of new projects like e.g. the assembly of the synchrotron light source (SLS), design studies of a new proton therapy facility, the ultracold neutron source and a new intensive secondary beam line for low energy muons. A large fraction of this report is devoted to research especially in the field of materials Science. The studies include large scale molecular dynamics computer simulations on the elastic and plastic behavior of nanostructured metals, complemented by experimental mechanical testing using micro-indentation and miniaturized tensile testing, as well as microstructural characterisation and strain field mapping of metallic coatings and thin ceramic layers, the latter done with synchrotron radiation

  19. Solar Energy Research Center Instrumentation Facility

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Thomas, J.; Papanikolas, John, P.

    2011-11-11

    SOLAR ENERGY RESEARCH CENTER INSTRUMENTATION FACILITY The mission of the Solar Energy Research Center (UNC SERC) at the University of North Carolina at Chapel Hill (UNC-CH) is to establish a world leading effort in solar fuels research and to develop the materials and methods needed to fabricate the next generation of solar energy devices. We are addressing the fundamental issues that will drive new strategies for solar energy conversion and the engineering challenges that must be met in order to convert discoveries made in the laboratory into commercially available devices. The development of a photoelectrosynthesis cell (PEC) for solar fuels production faces daunting requirements: (1) Absorb a large fraction of sunlight; (2) Carry out artificial photosynthesis which involves multiple complex reaction steps; (3) Avoid competitive and deleterious side and reverse reactions; (4) Perform 13 million catalytic cycles per year with minimal degradation; (5) Use non-toxic materials; (6) Cost-effectiveness. PEC efficiency is directly determined by the kinetics of each reaction step. The UNC SERC is addressing this challenge by taking a broad interdisciplinary approach in a highly collaborative setting, drawing on expertise across a broad range of disciplines in chemistry, physics and materials science. By taking a systematic approach toward a fundamental understanding of the mechanism of each step, we will be able to gain unique insight and optimize PEC design. Access to cutting-edge spectroscopic tools is critical to this research effort. We have built professionally-staffed facilities equipped with the state-of the-art instrumentation funded by this award. The combination of staff, facilities, and instrumentation specifically tailored for solar fuels research establishes the UNC Solar Energy Research Center Instrumentation Facility as a unique, world-class capability. This congressionally directed project funded the development of two user facilities: TASK 1: SOLAR

  20. Is operations research really research? | Manson | ORiON

    African Journals Online (AJOL)

    This paper takes a philosophical look at the Research in Operations Research. First, the questions "What is Research?" and "What is Operations Research?" are discussed. Next, the paper discusses why it is important to have a clear definition of research, especially in academia. The paper then discusses a research ...

  1. Large-scale User Facility Imaging and Scattering Techniques to Facilitate Basic Medical Research

    International Nuclear Information System (INIS)

    Miller, Stephen D.; Bilheux, Jean-Christophe; Gleason, Shaun Scott; Nichols, Trent L.; Bingham, Philip R.; Green, Mark L.

    2011-01-01

    measurement techniques including imaging and tomography. The next generation NSLS-II facility is now under construction. The Advanced Light Source (ALS) commissioned in 1993 has one of the world's brightest sources of coherent long wavelength x-rays suitable for probing biological samples in 3D. The Advanced Photon Source at Argonne National Laboratory also has a number of x-ray beamlines dedicated to imaging and tomography suitable for biological and medical imaging research. The Spallation Neutron Source (SNS) at Oak Ridge National Laboratory (ORNL) also has a number of beamlines suitable for studying the structure and dynamics of proteins and other biological systems. A neutron imaging and tomography beamline is currently being planned for SNS. Similarly, the High Flux Isotope Reactor (HFIR) also at ORNL has beamlines suitable for examining biological matter and has an operational imaging beamline. In addition, the production of medical isotopes is another important HFIR function. These user facilities have been intended to facilitate basic and applied research and were not explicitly designed with the intention to scan patients the same way a commercial medical imaging scanner does. Oftentimes the beam power is significantly more powerful than those produced by medical scanners. Thus the ionizing radiation effects of these beams must be considered when contemplating how these facilities can contribute to medical research. Suitable research areas involving user facilities include the study of proteins, human and animal tissue sample scanning, and in some cases, the study of non-human vertebrate animals such as various rodent species. The process for scanning biological and animal specimens must be approved by the facility biosafety review board. The national laboratories provide a number of imaging and scattering instruments which can be used to facilitate basic medical research. These resources are available competitively via the scientific peer review process for

  2. Development of the West Virginia University Small Microgravity Research Facility (WVU SMiRF)

    Science.gov (United States)

    Phillips, Kyle G.

    experimentation provided repeatability characteristics of the facility. Based on checkout instrumentation, Initial repeatability results indicated a drop time of 1.26 seconds at an average of 0.06g, with a standard deviation of 0.085g over the period of the drop, and a peak impact load of 28.72g, with a standard deviation of 10.73g, for a payload weight of 113.8 lbs. In order to thoroughly check out the facility, a full-scale, fully operational experiment was developed to create an experience that provides a comprehensive perspective of the end-user experience to the developer, so as to incorporate the details that may have been overlooked to the designer and/or developer, in this case, Kyle Phillips. The experiment that was chosen was to determine the effects of die swell, or extrudate swell, in reduced gravity. Die swell is a viscoelastic phenomenon that occurs when a dilatant, or shear-thickening substance is forced through a sufficient constriction, or "die," such that the substance expands, or "swells," downstream of the constriction, even while forming and maintaining a free jet at ambient sea level conditions. A wide range of dilatants exhibit die swell when subjected to the correct conditions, ranging from simple substances such as ketchup, oobleck, and shampoo to complex specially-formulated substances to be used for next generation body armor and high performance braking systems. To date, very few, if any, have researched the stabilizing effect that gravity may have on the phenomenon of die swell. By studying a fluid phenomenon in a reduced gravity environment, both the effect of gravity can be studied and the predominant forces acting on the fluid can be concluded. Furthermore, a hypothesis describing the behavior of a viscoelastic fluid particle employing the viscous Navier-Stokes Equations was derived to attempt to push the fluid mechanics community toward further integrating more fluid behavior into a unified mathematical model of fluid mechanics. While inconclusive

  3. Status of the support researches for the regulation of nuclear facilities decommissioning in Japan

    International Nuclear Information System (INIS)

    Masuda, Yusuke; Iguchi, Yukihiro; Kawasaki, Satoru; Kato, Masami

    2011-01-01

    In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the 'Prioritized Nuclear Safety Research Plan (August 2009)' of the Nuclear Safety Commission of Japan and the situation of operators facilities, 'Regulatory Support Research Plan between FY 2010-2014' was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3

  4. A ''dog gone'' restoration project: Remediation of an AEC research facility

    International Nuclear Information System (INIS)

    Huff, P.E.; Brooks, B.T.

    1994-01-01

    This facility was established in 1958 by the Atomic Energy Commission. Research at the facility originally focused on the health effects from chronic exposures to radionuclides, primarily strontium 90 ( 90 Sr) and radium 226 ( 226 Ra), using beagles to simulate radiation effects on humans. In 1988 the Department of Energy (DOE) decided to close out the research program, shut down the facility and turn it over to the tenant after remediation. This paper examines the remediation activities relative to Animal Hospitals 1 and 2 (AH-1 and AH-2), the cobalt 60 ( 60 Co) source and the Specimen Storage Room. Remediation of this facility took place over one year period beginning in August 1992. Portions of the facility not requiring remediation are now a part of an ongoing research facility. While excluded from areas where remediation took place, facility personnel and others were in close proximity to the remediation, sometimes separated only by a common building wall. This close proximity required remediation techniques that stressed contamination control

  5. Techniques for controlling air pollution from the operation of nuclear facilities. Report of a panel

    International Nuclear Information System (INIS)

    1966-01-01

    This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level.

  6. 9 CFR 354.210 - Minimum standards for sanitation, facilities, and operating procedures in official plants.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Minimum standards for sanitation, facilities, and operating procedures in official plants. 354.210 Section 354.210 Animals and Animal Products... sanitation, facilities, and operating procedures in official plants. The provisions of §§ 354.210 to 354.247...

  7. Safe operation and maintenance of research reactor

    International Nuclear Information System (INIS)

    Munsorn, S.

    1999-01-01

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U 3 O 8 - Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  8. Safe operation and maintenance of research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Munsorn, S. [Reactor Operation Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok (Thailand)

    1999-10-01

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U{sub 3}O{sub 8}- Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  9. Operational characteristics of the OMEGA short-wavelength laser fusion facility

    International Nuclear Information System (INIS)

    Soures, J.M.; Hutchison, R.; Jacobs, S.; McCrory, R.L.; Peck, R.; Seka, W.

    1984-01-01

    Twelve beams of the OMEGA, 24 beam direct-drive laser facility have been converted to 351-nm wavelength operation. The performance characteristics of this short-wavelength facility will be discussed. Beam-to-beam energy balance of +-2.3% and on-target energy, at 351-nm, in excess of 70 J per beam have been demonstrated. Long-term performance (>600 shots) of the system has been optimized by appropriate choice of index matching liquid, optical materials and coatings. The application of this system in direct-drive laser fusion experiments will be discussed

  10. The emergence of care facilities in Thailand for older German-speaking people: structural backgrounds and facility operators as transnational actors.

    Science.gov (United States)

    Bender, Désirée; Hollstein, Tina; Schweppe, Cornelia

    2017-12-01

    This paper presents findings from an ethnographic study of old age care facilities for German-speaking people in Thailand. It analyses the conditions and processes behind the development and specific designs of such facilities. It first looks at the intertwinement, at the socio-structural level, of different transborder developments in which the facilities' emergence is embedded. Second, it analyses the processes that accompany the emergence, development and organisation of these facilities at the local level. In this regard, it points out the central role of the facility operators as transnational actors who mediate between different frames of reference and groups of actors involved in these facilities. It concludes that the processes of mediation and intertwining are an important and distinctive feature of the emergence of these facilities, necessitated by the fact that, although the facilities are located in Thailand, their 'markets' are in the German-speaking countries of their target groups.

  11. A US Based Ultrafast Interdisciplinary Research Facility

    Science.gov (United States)

    Gueye, Paul; Hill, Wendell; Johnson, Anthony

    2006-10-01

    The US scientific competitiveness on the world arena has substantially decreased due to the lack of funding and training of qualified personnel. Most of the potential workforce found in higher education is composed of foreign students and post-docs. In the specific field of low- and high-field science, the European and Asian communities are rapidly catching-up with the US, even leading in some areas. To remain the leader in ultrafast science and technology, new visions and commitment must be embraced. For that reason, an international effort of more than 70 countries for a US-based interdisciplinary research facility using ultrafast laser technology is under development. It will provide research and educational training, as well as new venues for a strong collaboration between the fields of astrophysics, nuclear/high energy physics, plasma physics, optical sciences, biological and medical physics. This facility will consist of a uniquely designed high contrast multi-lines concept housing twenty experimental rooms shared between four beams:[0.1 TW, 1 kHz], [10 TW, 9 kHz], [100-200 TW, 10 Hz] and [500 TW, 10 Hz]. The detail schematic of this multi-laser system, foreseen research and educational programs, and organizational structure of this facility will be presented.

  12. Anti- and Hypermatter Research at the Facility for Antiproton and Ion Research FAIR

    International Nuclear Information System (INIS)

    Steinheimer, J; Xu, Z; Gudima, K; Botvina, A; Mishustin, I; Bleicher, M; Stöcker, H

    2012-01-01

    Within the next six years, the Facility for Antiproton and Ion Research (FAIR) is built adjacent to the existing accelerator complex of the GSI Helmholtz Center for Heavy Ion Research at Darmstadt, Germany. Thus, the current research goals and the technical possibilities are substantially expanded. With its worldwide unique accelerator and experimental facilities, FAIR will provide a wide range of unprecedented fore-front research in the fields of hadron, nuclear, atomic, plasma physics and applied sciences which are summarized in this article. As an example this article presents research efforts on strangeness at FAIR using heavy ion collisions, exotic nuclei from fragmentation and antiprotons to tackle various topics in this area. In particular, the creation of hypernuclei and antimatter is investigated.

  13. Co-Operative Advances in Behavioral Health and Performance Research and Operations

    Science.gov (United States)

    VanderArk, Stephen T.; Leveton, Lauren B.

    2011-01-01

    In organizations that engage in both operations and applied research, with operational needs guiding research questions and research informing improved operations, the ideal goal is a synergy of ideas and information. In reality, this ideal synergy is often lacking. Real-time operational needs driving day-to-day decisions, lack of communication, lag time in getting research advances plugged into operations can cause both areas to suffer from this gap between operations and research. At Johnson Space Center, the Behavior Health and Performance group (BHP) strives to bridge this gap by following a Human Research Program framework: Expectations of future operational needs identify the knowledge gaps; the gaps in turn guide research leading to a product that is transitioned into operations. Thus, the direction those of us in research take is in direct response to current and future needs of operations. Likewise, those of us in operations actively seek knowledge that is supported by evidence-based research. We make an ongoing effort to communicate across the research and operations gap by working closely with each other and making a conscious effort to keep each other informed. The objective of the proposed panel discussion is to demonstrate through the following presentations the results of a successful collaboration between research and operations and to provide ASMA members with more practical knowledge and strategies for building these bridges to serve our field of practice well. The panel will consist of six presenters from BHP operations, internal BHP research, and external research instigated by BHP who together represent the entire BHP Research Transition to Operations Framework

  14. Lewis Research Center space station electric power system test facilities

    Science.gov (United States)

    Birchenough, Arthur G.; Martin, Donald F.

    1988-01-01

    NASA Lewis Research Center facilities were developed to support testing of the Space Station Electric Power System. The capabilities and plans for these facilities are described. The three facilities which are required in the Phase C/D testing, the Power Systems Facility, the Space Power Facility, and the EPS Simulation Lab, are described in detail. The responsibilities of NASA Lewis and outside groups in conducting tests are also discussed.

  15. Process pump operating problems and equipment failures, F-Canyon Reprocessing Facility, Savannah River Plant

    International Nuclear Information System (INIS)

    Durant, W.S.; Starks, J.B.; Galloway, W.D.

    1987-02-01

    A compilation of operating problems and equipment failures associated with the process pumps in the Savannah River Plant F-Canyon Fuel Reprocessing Facility is presented. These data have been collected over the 30-year operation of the facility. An analysis of the failure rates of the pumps is also presented. A brief description of the pumps and the data bank from which the information was sorted is also included

  16. Construction of the neutron beam facility at Australia's OPAL research reactor

    International Nuclear Information System (INIS)

    Kennedy, Shane J.

    2006-01-01

    Australia's new research reactor, OPAL, has been designed principally for neutron beam science and radioisotope production. It has a capacity for 18 neutron beam instruments, located at the reactor face and in a neutron guide hall. The neutron beam facility features a 20 l liquid deuterium cold neutron source and cold and thermal supermirror neutron guides. Nine neutron beam instruments are under development, of which seven are scheduled for completion in early 2007. The project is approaching the hot-commissioning stage, when criticality will be demonstrated. Installation of the neutron beam transport system and neutron beam instruments in the neutron guide hall and at the reactor face is underway, and the path to completion of this project is relatively clear. This paper will outline the key features of the OPAL reactor, and will describe the neutron beam facility in particular. The status of the construction and a forecast of the program to completion, including commissioning and commencement of routine operation in 2007 will also be discussed

  17. 42 CFR 412.405 - Preadmission services as inpatient operating costs under the inpatient psychiatric facility...

    Science.gov (United States)

    2010-10-01

    ... under the inpatient psychiatric facility prospective payment system. 412.405 Section 412.405 Public... Services of Inpatient Psychiatric Facilities § 412.405 Preadmission services as inpatient operating costs under the inpatient psychiatric facility prospective payment system. The prospective payment system...

  18. A proposed regulatory policy statement on human factors requirements in the design and operation of Canadian nuclear facilities

    International Nuclear Information System (INIS)

    1986-10-01

    With the increasing complexity of new nuclear facilities and the extent to which automation is being applied, it is essential that the staff who operate a facility be considered as integral components in the design and safety analyses. This policy statement is proposed to indicate those areas of facility design and operation where the role of the human operator must be especially examined

  19. Construction and initial operation of the Advanced Toroidal Facility

    International Nuclear Information System (INIS)

    Bell, G.L.; Bell, J.D.; Benson, R.D.

    1989-08-01

    The Advanced Toroidal Facility (ATF) torsatron was designed on a physics basis for access to the second stability regime and on an engineering basis for independent fabrication of high-accuracy components. The actual construction, assembly, and initial operation of ATF are compared with the characteristics expected during the design of ATF. 31 refs., 19 figs., 2 tabs

  20. Jordan Research and Training Reactor (JRTR) Utilization Facilities

    International Nuclear Information System (INIS)

    Xoubi, N.

    2013-01-01

    Jordan Research and Training Reactor (JRTR) is a 5 MW light water open pool multipurpose reactor that serves as the focal point for Jordan National Nuclear Centre, and is designed to be utilized in three main areas: Education and training, nuclear research, and radioisotopes production and other commercial and industrial services. The reactor core is composed of 18 fuel assemblies, MTR plate type 19.75% enriched uranium silicide (U 3 Si 2 ) in aluminium matrix, and is reflected on all sides by beryllium and graphite. The reactor power is upgradable to 10 MW with a maximum thermal flux of 1.45×10 14 cm -2 s -1 , and is controlled by a Hafnium control absorber rod and B 4 C shutdown rod. The reactor is designed to include laboratories and classrooms that will support the establishment of a nuclear reactor school for educating and training students in disciplines like nuclear engineering, reactor physics, radiochemistry, nuclear technology, radiation protection, and other related scientific fields where classroom instruction and laboratory experiments will be related in a very practical and realistic manner to the actual operation of the reactor. JRTR is designed to support advanced nuclear research as well as commercial and industrial services, which can be preformed utilizing any of its 35 experimental facilities. (author)

  1. Design study of the underground facilities, the Mizunami Underground Research Laboratory

    International Nuclear Information System (INIS)

    Ishizuka, Mineo; Noda, Masaru; Shiogama, Yukihiro; Adachi, Tetsuya

    1999-02-01

    Geoscientific research on the deep geological environment has been performed by Japan Nuclear Cycle Development Institute (JNC). This research is supported by the 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. The Mizunami Underground Research Laboratory (MIU) is planned to be constructed at the Shobasama-bora site belonging to JNC. A wide range of geoscientific research and development activities which have been previously performed in and around the Tono mine is planned to be expanded in the laboratory. The MIU consisted of surface and underground facilities excavated to a depth of about 1,000 meters. In this design study, the overall layout and basic design of the underground facility and the composition of the overall research program, includes the construction of the underground facility are studied. Based on the concept of the underground facility which have been developed in 1998, the research activities which will be performed in the MIU are selected and the overall research program is revised in this year. The basic construction method and the construction equipment are also estimated. (author)

  2. Design study of underground facility of the Mizunami Underground Research Laboratory

    International Nuclear Information System (INIS)

    Ishizuka, Mineo; Noda, Masaru; Shiogama, Yukihiro; Adachi, Tetsuya

    1999-02-01

    Geoscientific research on deep geological environment has been performed by Japan Nuclear Cycle Development Institute (JNC). This research is supported by the 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. The Mizunami Underground Research Laboratory (MIU) is planned to be constructed at Shobasama-bora site belonging to JNC. A wide range of geoscientific research and development activities which have been previously performed in and around the Tono mine is planned to be expanded in the laboratory. The MIU is consisted of surface and underground facilities down to the depth of about 1,000 meters. In this design study, the overall layout and basic design of the underground facility and the composition of the overall research program which includes the construction of the underground facility are studied. Based on the concept of the underground facility which have been developed last year, the research activities which will be performed in the MIU are selected and the overall research program is revised in this year. The basic construction method and the construction equipment are also estimated. (author)

  3. Safety Evaluation Report related to the renewal of the operating license for the Westinghouse research reactor at Zion, Illinois (Docket No. 50-87)

    International Nuclear Information System (INIS)

    1984-09-01

    This Safety Evaluation Report, for the application filed by the Westinghouse Electric Company, for renewal of operating license number R-119 to continue to operate the research reactor, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is operated by Westinghouse and is located in Zion, Illinois. The staff concludes that the reactor facility can continue to be operated by Westinghouse without endangering the health and safety of the public

  4. The advanced neutron source - A world-class research reactor facility

    International Nuclear Information System (INIS)

    Thompson, P.B.; Meek, W.E.

    1993-01-01

    The advanced neutron source (ANS) is a new facility being designed at the Oak Ridge National Laboratory that is based on a heavy-water-moderated reactor and extensive experiment and user-support facilities. The primary purpose of the ANS is to provide world-class facilities for neutron scattering research, isotope production, and materials irradiation in the United States. The neutrons provided by the reactor will be thermalized to produce sources of hot, thermal, cold, very cold, and ultracold neutrons usable at the experiment stations. Beams of cold neutrons will be directed into a large guide hall using neutron guide technology, greatly enhancing the number of research stations possible in the project. Fundamental and nuclear physics, materials analysis, and other research pro- grams will share the neutron beam facilities. Sufficient laboratory and office space will be provided to create an effective user-oriented environment

  5. Operational experience of the fuel cleaning facility of Joyo

    International Nuclear Information System (INIS)

    Mukaibo, R.; Matsuno, Y.; Sato, I.; Yoneda, Y.; Ito, H.

    1978-01-01

    Spent fuel assemblies in 'Joyo', after they are taken out of the core, are taken to the Fuel Cleaning Facility in the reactor service building and sodium removal is done. The cleaning process is done by cooling the assembly with argon gas, steam charging and rinsing by demineralized water. Deposited sodium was 50 ∼ 60 g per assembly. The sodium and steam reaction takes about 15 minutes to end and the total time the fuel is placed in the pot is about an hour. The total number of assemblies cleaned in the facility was 95 as of November 1977. In this report the operational experience together with discussions of future improvements are given. (author)

  6. Operational experience of the fuel cleaning facility of Joyo

    Energy Technology Data Exchange (ETDEWEB)

    Mukaibo, R; Matsuno, Y; Sato, I; Yoneda, Y; Ito, H [O-arai Engineering Centre, PNC, Ibaraki-ken, Tokio (Japan)

    1978-08-01

    Spent fuel assemblies in 'Joyo', after they are taken out of the core, are taken to the Fuel Cleaning Facility in the reactor service building and sodium removal is done. The cleaning process is done by cooling the assembly with argon gas, steam charging and rinsing by demineralized water. Deposited sodium was 50 {approx} 60 g per assembly. The sodium and steam reaction takes about 15 minutes to end and the total time the fuel is placed in the pot is about an hour. The total number of assemblies cleaned in the facility was 95 as of November 1977. In this report the operational experience together with discussions of future improvements are given. (author)

  7. Safety-evaluation report related to the renewal of the operating license for the Cornell University TRIGA Research Reactor. Docket No. 50-157

    International Nuclear Information System (INIS)

    1983-08-01

    This Safety Evaluation Report for the application filed by the Cornell University for a renewal of Operating License R-80 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by Cornell University and is located on the Cornell campus in Ithaca, New York. The staff concludes that the TRIGA reactor facility can continue to be operated by Cornell without endangering the health and safety of the public

  8. Small Multi-Purpose Research Facility (SMiRF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Small Multi-Purpose Research Facility (SMiRF) evaluates the performance of the thermal protection systems required to provide long-term storage (up to 10 years)...

  9. Research nuclear reactor operation management

    International Nuclear Information System (INIS)

    Preda, M.; Carabulea, A.

    2008-01-01

    Some aspects of reactor operation management are highlighted. The main mission of the operational staff at a testing reactor is to operate it safely and efficiently, to ensure proper conditions for different research programs implying the use of the reactor. For reaching this aim, there were settled down operating plans for every objective, and procedure and working instructions for staff training were established, both for the start-up and for the safe operation of the reactor. Damages during operation or special situations which can arise, at stop, start-up, maintenance procedures were thoroughly considered. While the technical skill is considered to be the most important quality of the staff, the organising capacity is a must in the operation of any nuclear facility. Staff training aims at gaining both theoretical and practical experience based on standards about staff quality at each work level. 'Plow' sheet has to be carefully done, setting clear the decision responsibility for each person so that everyone's own technical level to be coupled to the problems which implies his responsibility. Possible events which may arise in operation, e.g., criticality, irradiation, contamination, and which do not arise in other fields, have to be carefully studied. One stresses that the management based on technical and scientific arguments have to cover through technical, economical and nuclear safety requirements a series of interlinked subprograms. Every such subprograms is subject to some peculiar demands by the help of which the entire activity field is coordinated. Hence for any subprogram there are established the objectives to be achieved, the applicable regulations, well-defined responsibilities, training of the personnel involved, the material and documentation basis required and activity planning. The following up of positive or negative responses generated by experiments and the information synthesis close the management scope. Important management aspects

  10. Meeting the challenges of bringing a new base facility operation model to Gemini Observatory

    Science.gov (United States)

    Nitta, Atsuko; Arriagada, Gustavo; Adamson, A. J.; Cordova, Martin; Nunez, Arturo; Serio, Andrew; Kleinman, Scot

    2016-08-01

    The aim of the Gemini Observatory's Base Facilities Project is to provide the capabilities to perform routine night time operations with both telescopes and their instruments from their respective base facilities without anyone present at the summit. Tightening budget constraints prompted this project as both a means to save money and an opportunity to move toward increasing remote operations in the future. We successfully moved Gemini North nighttime operation to our base facility in Hawaii in Nov., 2015. This is the first 8mclass telescope to completely move night time operations to base facility. We are currently working on implementing BFO to Gemini South. Key challenges for this project include: (1) This is a schedule driven project. We have to implement the new capabilities by the end of 2015 for Gemini North and end of 2016 for Gemini South. (2) The resources are limited and shared with operations which has the higher priority than our project. (3) Managing parallel work within the project. (4) Testing, commissioning and introducing new tools to operational systems without adding significant disruptions to nightly operations. (5) Staff buying to the new operational model. (6) The staff involved in the project are spread on two locations separated by 10,000km, seven time zones away from each other. To overcome these challenges, we applied two principles: "Bare Minimum" and "Gradual Descent". As a result, we successfully completed the project ahead of schedule at Gemini North Telescope. I will discuss how we managed the cultural and human aspects of the project through these concepts. The other management aspects will be presented by Gustavo Arriagada [2], the Project Manager of this project. For technical details, please see presentations from Andrew Serio [3] and Martin Cordova [4].

  11. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

    1994-10-01

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

  12. Conjunctive operation of river facilities for integrated water resources management in Korea

    Directory of Open Access Journals (Sweden)

    H. Kim

    2016-10-01

    Full Text Available With the increasing trend of water-related disasters such as floods and droughts resulting from climate change, the integrated management of water resources is gaining importance recently. Korea has worked towards preventing disasters caused by floods and droughts, managing water resources efficiently through the coordinated operation of river facilities such as dams, weirs, and agricultural reservoirs. This has been pursued to enable everyone to enjoy the benefits inherent to the utilization of water resources, by preserving functional rivers, improving their utility and reducing the degradation of water quality caused by floods and droughts. At the same time, coordinated activities are being conducted in multi-purpose dams, hydro-power dams, weirs, agricultural reservoirs and water use facilities (featuring a daily water intake of over 100 000 m3 day−1 with the purpose of monitoring the management of such facilities. This is being done to ensure the protection of public interest without acting as an obstacle to sound water management practices. During Flood Season, each facilities contain flood control capacity by limited operating level which determined by the Regulation Council in advance. Dam flood discharge decisions are approved through the flood forecasting and management of Flood Control Office due to minimize flood damage for both upstream and downstream. The operational plan is implemented through the council's predetermination while dry season for adequate quantity and distribution of water.

  13. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    International Nuclear Information System (INIS)

    Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

    1999-01-01

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  14. Holifield Heavy Ion Research Facility. Phase II

    International Nuclear Information System (INIS)

    Ball, J.B.; Hudson, E.D.; Lord, R.S.; Johnson, J.W.; Martin, J.A.; McNeilly, G.S.; Milner, W.T.; Mosko, S.W.; Sayer, R.O.; Robinson, R.L.

    1979-01-01

    The Holifield Heavy Ion Research Facility, with the completion of Phase I in late 1979, will include the Oak Ridge Isochronous Cyclotron (ORIC) and associated research areas, the new 25 MV tandem accelerator with new research areas for tandem beams, and modifications to utilize the ORIC as a booster accelerator. The combination of the tandem and ORIC will provide beam energies of 25 MeV/A for light heavy ions and 6 MeV/A up to A = 160. This paper discusses plans for a Phase II expansion of the facility to include an isochronous cyclotron with superconducting magnet and reconfiguration of the existing research areas and the ORIC vault to handle the higher energy beams from the new cyclotron. The new booster cyclotron is a low-flutter high-spiral design patterned after the MSU K = 800 design, with a central magnetic field of about 5 tesla and an extraction radius of 1 meter. The new beam transport system will incorporate an rf beam-splitter system that will be able to deliver successive beam pulses to two or three experiment areas

  15. Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

    International Nuclear Information System (INIS)

    2009-01-01

    In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

  16. Charger 1: A New Facility for Z-Pinch Research

    Science.gov (United States)

    Taylor, Brian; Cassibry, Jason; Cortez, Ross; Doughty, Glen; Adams, Robert; DeCicco, Anthony

    2017-01-01

    Charger 1 is a multipurpose pulsed power laboratory located on Redstone Arsenal, with a focus on fusion propulsion relevant experiments involving testing z-pinch diodes, pulsed magnetic nozzle and other related physics experiments. UAH and its team of pulsed power researchers are investigating ways to increase and optimize fusion production from Charger 1. Currently the team has reached high-power testing. Due to the unique safety issues related to high power operations the UAH/MSFC team has slowed repair efforts to develop safety and operations protocols. The facility is expected to be operational by the time DZP 2017 convenes. Charger 1 began life as the Decade Module 2, an experimental prototype built to prove the Decade Quad pinch configuration. The system was donated to UAH by the Defense Threat Reduction Agency (DRTA) in 2012. For the past 5 years a UAH/MSFC/Boeing team has worked to refurbish, assemble and test the system. With completion of high power testing in summer 2017 Charger 1 will become operational for experimentation. Charger 1 utilizes a Marx Bank of 72 100-kV capacitors that are charged in parallel and discharged in series. The Marx output is compressed to a pulse width of approximately 200 ns via a pulse forming network of 32 coaxial stainless steel tubes using water as a dielectric. After pulse compression a set of SF6 switches are triggered, allowing the wave front to propagate through the output line to the load. Charger 1 is capable of storing 572-kJ of energy and time compressing discharge to less than 250 ns discharge time producing a discharge of about 1 TW of discharge with 1 MV and 1 MA peak voltage and current, respectively. This capability will be used to study energy yield scaling and physics from solid density target as applied to advanced propulsion research.

  17. Operational readiness review for the Waste Experimental Reduction Facility. Final report

    International Nuclear Information System (INIS)

    1993-11-01

    An Operational Readiness Review (ORR) at the Idaho National Engineering Laboratory's (INEL's) Waste Experimental Reduction Facility (WERF) was conducted by EG ampersand G Idaho, Inc., to verify the readiness of WERF to resume operations following a shutdown and modification period of more than two years. It is the conclusion of the ORR Team that, pending satisfactory resolution of all pre-startup findings, WERF has achieved readiness to resume unrestricted operations within the approved safety basis. ORR appraisal forms are included in this report

  18. Safety Evaluation Report related to the construction permit and operating license for the research reactor at the University of Texas (Docket No. 50-602)

    International Nuclear Information System (INIS)

    1985-05-01

    This Safety Evaluation Report for the application filed by the University of Texas for a construction permit and operating license to construct and operate a TRIGA research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Texas and is located at the university's Balcones Research Center, about 7 miles (11.6 km) north of the main campus in Austin, Texas. The staff concludes that the TRIGA reactor facility can be constructed and operated by the University of Texas without endangering the health and safety of the public

  19. The internationalisation of research facilities

    International Nuclear Information System (INIS)

    Sabine, T.M.

    1999-01-01

    Full text: During the past twenty five years arrangements have been made for sharing the use of major national research facilities amongst the world community of neutron users. The administrative requirements are simple. Scientists are invited to apply for measurement time. The scientific merit of the application is assessed by a committee appointed by the host organisation. If the application is considered to have sufficient merit time is allocated. The only costs to the user are transport and living expenses. These arrangements have advantages for users and for hosts. The user can apply for time on the most suitable instrument. The host in the user country is freed from the responsibility of supplying all instruments. It can specialise in those instruments in which it has particular expertise. The host retains, through its committee, complete control over the use of instruments. The amount of time allocated to international users is dependent on the national demand. The result is efficient use of national facilities. An equally important result is the interaction between members of the international scientific community. Australian scientists routinely use overseas facilities however Australia has refused to join the international group. There is international resentment to this attitude. We have, for example powder diffraction facilities which others wish to use. We have no small-angle scattering facilities and must do our experiments at international centres. I will argue that we should join the international community now. The capacity of the replacement reactor will be far greater than the internal Australian requirements. We will become the natural host for users from countries in the Asian region. To enable us to make a smooth transition to this stage we should immediately advertise an international program for HIFAR

  20. Irradiation facilities in JRR-3M

    International Nuclear Information System (INIS)

    Ohtomo, Akitoshi; Sigemoto, Masamitsu; Takahashi, Hidetake

    1992-01-01

    Irradiation facilities have been installed in the upgraded JRR-3 (JRR-3M) in Japan Atomic Energy Research Institute (JAERI). There are hydraulic rabbit facilities (HR), pneumatic rabbit facilities (PN), neutron activation analysis facility (PN3), uniform irradiation facility (SI), rotating irradiation facility and capsule irradiation facilities to carry out the neutron irradiation in the JRR-3M. These facilities are operated using a process control computer system to centerize the process information. Some of the characteristics for the facilities were satisfactorily measured at the same time of reactor performance test in 1990. During reactor operation, some of the tests are continued to confirm the basic characteristics on facilities, for example, PN3 was confirmed to have enough performance for activation analysis. Measurement of neutron flux at all irradiation positions has been carried out for the equilibrium core. (author)